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PNE-229FF I N A L R E P O R T

A L O v V & r / i i r C / peacefu l uses for nuc lear exp losivesU N I T E D S T A T E S A T O M I C E N E R G Y C O M M I S S I O N / P L O W S H A R E P R O G R A M

projectN E V A D A T E S T S I T E / J U L Y 6 , 1 9 6 2

L a s V e g a s

S o m e R a d i o c h e m i c a l a n d P h y s i ca l M e a s u r e m e n t s ofD e b r is f r o m a n U n d e r g r o u n d N u c l e a r D e t o n a t i o n

W. B. LaneU. S. NAVAL RADIOLOGICAL DEFENSE LABORATORY ISSUED: JANUARY 7, 1964

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L E G A L N O T I C EThis report was prepared as an account of G overnment sponsored work. N either the UnitedStates, nor the Commission, nor any person acting on behalf of the Commission:A. Makes anywarranty or representation, expressed or implied, with respect to the accu-racy, c omp leteness, or usefulne ss of the Information contained in this report, or that the useof any information, apparatus, method, or proc ess disc losed In this report may not Infringeprivately owned rights; orB. Assu mes any liabilities with respec t to the use of, or for damages resulting from theuse of any Information, apparatus, method, or process disclosed in this report.As used In the above, "person acting on behalf of the Commission" includes any em-ployee or contractor of the Commission, or employee of such contractor, to the extent thatsuch employee or contractor of the Commission, or employee of such contractor prepares,disseminates, or provides access to, any information pursuant to his employment or contractwith the Commission, or his employment with such contractor.

Thi s r e p or t ha s be e n re p roduc e d d i re c t l y f rom the be s tava i lable copy.Pr int ed in USA. P ri ce $ 2.5 0. Available from the Office ofTe c hn ic a l S e rv i c e s , D e pa r tme n t of Com m e rc e , Wa sh ing ton25, D. C.

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DISCLAIMER

This report was prepared as an account of work sponsored by anagency of the United States Government. Neither the United StatesGovernment nor any agency Thereof, nor any of their employees,makes any warranty, express or implied, or assumes any legalliability or responsibility for the accuracy, completeness, orusefulness of any information, apparatus, product, or processdisclosed, or represents that its use would not infringe privatelyowned rights. Reference herein to any specific commercial product,process, or service by trade name, trademark, manufacturer, orotherwise does not necessarily constitute or imply its endorsement,recommendation, or favoring by the United States Government or anyagency thereof. The views and opinions of authors expressed hereindo not necessarily state or reflect those of the United StatesGovernment or any agency thereof.

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DISCLAIMER

Portions of this document may be illegible inelectronic image products. Images are producedfrom the best available original document.

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NUCLEAR EXPLOSIONS - PEACEFUL APPLICATIONS

P R O J E C T S E D A NP N E Z 2 9 F

S OM E R A D I O C H E M I C A L A N D P H Y S I C A L M E A S U R E M E N T S O FD E B R I S F R O M A N U N D E R G R O U N D N U C L E A R D E T O N A T I O N

W . B . L a n e , P r o j e c t O f f i c e rU . S. N a v a l R a d i o l o g i c a l D e f e n s eL a b o r a t o r yC i v i l E f f e c t s T e s t G r o u pS an F r a n c i s c o , C a l i f o r n i a

J u n e 1 9 6 3

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ABSTRACTEallout samples were collected from 2600 feet to

19,000 feet from ground zero in order to determine themass per unit area, gamma activity per unit area, particlesize distribution and specific activity versus particlesize of the fallout; to determine the gamma decay rateand spectra of the samples; to perform leaching and exchange studies on the radioactive debris; to measure therelease of gaseous fission product iodine; and to determine the radiochemical composition of the fallout particulate .

Twenty collectors (2 ft x 2 ft x 2 in. deep) wereplaced in the downwind sector at increasing distances.An iodine gas sampler was located approximately two milesdownwind.

The fallout was well-distributed over the stationarray, and all collectors received significant deposits.

Analysis of the debris was performed at the NevadaTest Site.

Airborne iodine fission products were found in thecontaminated field downwind from ground zero, and iodinefission products were found to volatilize or be otherwisereleased from particulate fallout.

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Gamma decay measurements showed no evidence of radionuclide fractionation in debris from different locations,nor among different particle size fractions. Pulse heightdistributions also indicated no significant fractionationof gamma emitting radionuclides.

A 4- ionization chamber decay rate measurementshowed excellent agreement with a computed decay rate.

Measurements of mass and activity distributionsindicate that the radionuclides are associated with thevolume of the particle rather than with its surface area.

Radiochemical data are presented but extensiveanalysis was not attempted.

Sufficient data were obtained to meet all projectobjectives.

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PREFACEThe author wishes to acknowledge the contribution

made by Dr. Carl F. Miller, Assistant Director of Post-attack Research, Office of Civil Defense, Department ofDefense, in the initiation of the project, the design ofthe iodine experiment, and the execution of the fieldphase. Thanks are due to P. D. LaRiviere, ProjectLeader of Project 2.9 and 2.11 Small Boy, for makingavailable the U. S. Naval Radiological Defense Laboratory(HEEL) analytical facilities at the Nevada Test Site,and for devising the iodine data treatment.

Credit for the radiochemistry must go to membersof Project 2.10 Small Boy. Dr. E. C. Freiling, ProjectLeader, F. K. Kawahara, Assistant Project Leader, andL. R. Bunney, Deputy Project Leader of USNRDL distributedthe samples, specified the radionuclides to be determined,and converted the raw data to comparable units (fissions).

k

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CONTENTSABSTRACT 2PREFACE kCHAPTER 1 INTRODUCTION 71.1 Objectives 71.2 Background 71.3 Theory 9CHAPTER 2 PROCEDURE 11

2.1 Planning 112.2 Instrumentation 122.2.1 Field Collectors 122.2.2 Analytical Facilities 132.3 Collector Placement and Recovery 152.4 Analytical Procedures 162.4.1 Mass and Activity Distribution byParticle Size 162.4.2 Gaseous Fission Product Iodine 182.4-3 Leaching 192.4.4 Exchange 202.4.5 Radiochemical Determinations 20CHAPTER 3 RESULTS AND DISCUSSION 243.1 Field Collections 2 k3.2 Gamma Activity and Physical Propertiesof Debris 253.2.1 Gross Mass and Scintillation CounterMeasurements 253.2.2 Gamma Decay Rates by 4-n IonizationChamber 263.2.3 Mass and Activity Distribution byParticle Size 273.3 Volatility of Fission Product Iodine 28

3-4 Leaching of Gamma Emitters From Debris toVarious Solutions 313-5 Exchange of Gamma Emitters From Debris toClay and Adobe 313.6 Pulse Height Distributions 323.7 Radiochemistry 323.8 Significance of Data 34CHAPTER k CONCLUSIONS 83REFERENCES 85

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TABLES2.1 Station Locations 233.1 Gamma Decay Rates by Scintillation Counter . . . . 353.2 Gamma Activity and Gross Mass of DebrisCollected 363.3 Gamma Decay Rates by 4- Ionization Chamber. . . . 373.4 Mass and Activity Distributions of Debris 543.5 Gaseous Iodine Measured From Shot TimeUntil D+l 573.6 Loss of Iodine by Air Exposure 583.7 Three Day Leaching 593.8 Eight Day Leaching 603.9 Three Day Exchange 6l3.10 NRDL Sedan Radiochemical Results 62A.l Scintillation Counting Raw Data 87A.2 4-jt Ionization Chamber Raw Decay Data 88A.3 4-ir Ionization Chamber Raw Data for ActivityDistribution on Particles 104A.4 Raw Radiochemical Data 106

FIGURES2.1 Sedan Site Showing Sample Stations 233.1 Coincidence Correction for Gamma ScintillationCounter 713.2 Standard Decay Curve for Scintillation Counterand Station 7 Decay 7 23.3 Standard 4-n Ionization Chamber Decay Curveand Computed Decay Curve 733.4 Loss of Iodine From Particulate Debris by AirExposure 74

3-5 Pulse Height Distributions of IodinePrecipitates 753.6 Pulse Height Distributions of LeachedActivities f63.7 Pulse Height Distribution of Activity From

Different Locations 773.8 Pulse Height Distribution of Activity FromDifferent Locations 7 83.9 Pulse Height Distribution of Activity FromDifferent Locations 7 93.10 Pulse Height Distributions of Sieved Fractions. . 803.11 Pulse Height Distributions of Sieved Fractions. . 8l3.12 Pulse Height Distributions of Sieved Fractions. . 8 2

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CHAPTER 1INTRODUCTION

1.1 OBJECTIVESa. To make quantitative collections of debris in order

to determine mass per unit area, ionization decay rate andgamma spectra, mass and activity distribution as a functionof particle size and radiochemical composition of sizeseparated fractions.

b. To measure the release of gaseous iodine fissionproduct.

c. To study the exchange of fission products rromthe debris to commercial clay and adobe soil, and the leaching of fission products by solutions of pH 1, pH 6, andpH 10.

1 . 2 BACKGROUNDPlowshare is a program in the Division of Peaceful

Nuclear Explosives of the Atomic Energy Commission (AEC)and is administered by the AEC's San Francisco OperationsOffice. Scientific and technical phases of Project Sedanof the Plowshare Program were carried out under the direction of the University of California Lawrence RadiationLaboratory (UCRL).

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Project Sedan was the first nuclear excavation experiment to develop and demonstrate earth moving techniques .

The use of nuclear detonations for building dams,excavating harbors or digging canals, involves some venting of radioactive debris from the crater and the depo

sition of the debris around the site. The measurement ofthis contaminating event and the evaluation of the resulting radiological situation is absolutely necessary todemonstrate operational safety.

Coincident with the time of the Sedan project, theU. S. Naval Radiological Defense Laboratory (NRDL) hadextensive facilities and personnel at the Nevada TestSite to conduct Projects 2.9* 2.10 and 2.11 at OperationSmall Boy. A slight adjustment in effort made possibletheir participation in Sedan.

The NRDL has participated in fallout programs inOperations Jangle (1951), Ivy (1952), Castle (19 5 M,Wigwam (l955)> Teapot (1955)> Redwing (1956), Plumbbob(1957)> and Hardtack (1958). In addition to the WeaponsTest Reports resulting directly from these studies, therelated publications which have been issued have contributed to our present understanding of many aspects of

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radioactive debris formation, transport, deposition, andgamma radiations.

The present work covering a limited number of samplingpoints Is intended to provide badly needed fallout formation checkpoints for the existing formation, fractionation, and deposition models, and to extend our knowledgeof the basic mechanisms involved in interactions offission products with soil particles.

1.3 THEORYThe identification and the evaluation of radiological

effects produced by nuclear explosions requires informationand data on radioactive debris. The data needed may bedivided into four sub-program study areas. These are:(l) the formation of debris; (2) the distribution ofdebris; (3) the radiological exposure environment; and(4) the alteration of the exposure environment by counter-measures .

Theoretical studies, data compilations, or empiricalgeneralizations of experimental data in each of the foursub-programs may be considered in terms of several models.A thermochemical model of the formation process, a meteorological model of the distribution process, a hazard modelof the exposure environment, and a countermeasure systemmodel for methods that can be used to change, in a

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desired way, the exposure environment. The collections,field measurements and analyses of this project contributemost directly to the formation or evaluation of the theoretical or empirical models in all of the sub-program areas.

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CHAPTER 2PROCEDURE

2.1 PLANNINGThe proposal to participate in Sedan was submitted on

28 June 1962, and the sample collection phase of the project was planned and executed in the ensuing 8 days beforeshot time. A restriction was placed on Sedan participationin that it was not to interfere with either Small Boy orJohnie Boy projects.

Estimates of the location of the fallout pattern,mass per unit area, particle size range, and 1 hr gammaionization rates were not available to this project forplanning purposes. An acceptable wind speed and directionfor shot time was available, and sampling locations wereselected along convenient roads in the downwind sectorencompassed by 60 east and 6b west of north, fromground zero. No surveys were used, but an attempt wasmade to select sampling stations near other surveyedpoints. Table 2.1 and Figure 2.1 show the locationsaccording to LRL map L6-14734A.

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2.2 INSTRUMENTATION2.2.1 Field Collectors. The collectors were aluminum

trays 2 ft x 2 ft x 2 in. deep. They were exposed atlocations where significant mass levels were expected.In order to meet the conflicting requirements that allparticles contacting the interior of the collector beretained unaltered, yet be recoverable by dry techniques,two things were done: (l) all interior surfaces weredegreased prior to use and (2) an insert of aluminumlouvers, inclined 45 to the vertical, was provided tocreate dead air cells, thereby minimizing blow-out offine particles. I n addition, the louvers served toprevent bounce-out of the large (plus 5 00 micron) particles. The inserts were constructed so that they couldbe completely disassembled for ease of decontamination.

A gaseous iodine collection was made in the field.The devices employed two intakes; one intake sampled the

airborne iodine, the other sampled the airborne iodineplus the iodine which was liberated from fallout depositedin a 1 foot diameter funnel. A funnel was connected toan Anderson Aerosol Sampler (a five stage impactiondevice with a millipore filter) so that any gaseousproducts evolved from the fallout would be carried

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through the system by the 38 liter/min air flow. I n thefirst case the entrance to the Anderson Sampler wascovered with a hood to exclude all particulate fallout,and an identical flow rate was used. A gasoline drivenmotor generator powered a vacuum pump which drew 3*8liters of air per minute through each of two metering

>

orifices. The orifices were connected to bubble columnscontaining 7 5 inl of 0.05M sodium thiosulfate solution.The bubblers were in turn connected to the AndersonSamplers. The millipore filters insured that no particulate matter reached the thiosulfate.

2.2.2 Analytical Facilities. The analytical facilities of Project 2.9 Small Boy were used for analysis ofthe Sedan samples.

A large tent housed a Rotap sieving apparatus andsedimentation columns for sub-sieve analysis. A balanceroom was partitioned off in one end of the tent. Achemistry trailer provided complete laboratory apparatusand reagents. Another trailer housed the radiationdetection instruments listed below:

Two end-on low-geometry Nal scintillation counterswith l-l/2 inch diameter by 1 inch thick crystals wereavailable. The source detector distance was 4l inches,

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and the floor area and door were large enough to accept2 feet by 2 feet collection trays. A 2-inch thick leadshield surrounded the whole. The detector was mounted ona Dumont 6292 multiplier phototube whose output drove again-of-ten preamplifier and a cathode follower. The

signal was fed into a Systron model 1091-S scaler whichwas controlled by a Nuclear Dual Timer. A John FlukeModel 4l2A high voltage supply provided dynode stringvoltage for the multiplier phototube.

All readings were normalized to a standard responseof 32,100 counts/min for 100 |jg of Ra on the floor of the

counter. This standardization permits direct application,if desired, of the calibration data for a similar counterreported in Reference 1.

One 4-pi-gamma ionization chamber was argon-filled to6b0 psig at 7 0 F. This steel chamber was eleven inchesin diameter and fourteen inches high, with a reentrant

sample thimble 1-3/4 inch internal diameter by 12 inchdeep. The entire chamber was shielded by 3 inches oflead. Current produced in the chamber by ionizing radiation was applied to suitable load resistors; the resultant voltage drop drove a plate difference amplifier andwas read out on a microammeter. The useful ionization

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current output ranged between 4 x 10 " and 3 x 10 ma.Al l readings were normalized to a standard response of5.60 x 10 ma for 100 pg of radium. Coristruction andabsolute response details may be found in Reference 2.

One Penco 100-channel gamma ray pulse-height analyzer'employed a 4-inch diameter by 4-inch high Nal(Tl) crystaldetector. Samples were counted using a l/2 inch or 3 Ainch diameter collimator, both 6 inches long, or wereplaced directly on the crystal, depending on samplestrength. The instrument is fully described in Reference 3-

All counters were cross-calibrated with at leastone kind of reference standard. Actual fallout collections were also used to determine the effects of variousgeometries and gamma spectral changes with time.

2.3 COLLECTOR PLACEMENT AND RECOVERYOn D-2 and D-l a tray collector was placed at each

of the locations noted in Table 2.1. The trays weresecured to the ground by a cross-wire which was anchoredto a tent stake on one side and a steel fence post on

1 This equipment was provided by and operated by Dr. J. M.Ferguson and F. M. Tomnovec of CETO Operation Bren.

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the other. The station location was identified by amagenta flag at the top of the steel post.

At 06b0 hours on 6 July 1962 the iodine gas samplerwas placed at station 19 and the motor generator started.Three collectors were exposed at this station.

The Sedan device was designed for a yield of 100 + 15KT, and it was detonated at a depth of 635 feet at 1000 hourson 6 July 1962. The resulting crater was about 1200 feetin diameter and 320 feet deep, with a volume of some 7 5million cubic yards. The three collectors and the iodinegas sampler were recovered from station 19 at 17 00 houus on7 July 1962. Collectors from stations 9, 10, 12, 13, 14and 20 were recovered at 1700 houison 8 July.

Collectors from stations 6, 7 , 8 , 11 , 15 , 16, 17 and18 were recovered at 1400 houis on 10 July 1962.

2.4 ANALYTICAL PROCEDURES2.4.1 Mass and Activity Distribution by Particle

Size. Material in the collectors was assayed for grossgamma activity in the low-geometry scintillation counterbefore any further handling losses were incurred. Thecollectors were then placed in large polyethylene bags,disassembled, and as the metal parts were brushed clean,

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they were removed, thus leaving the debris inside the bag.This procedure minimized losses and kept the aerosol toan acceptable level in the working spaces. The collectorcomponents were then reassembled and recounted to permitthe assessment of removal losses.

The debris from each collector was weighed and quartered to obtain a representative fraction for dry sieving.This fraction was Ro-tapped for 10 minutes through a nestof six Tyler sieves, numbers 7 , 1 2, 24, 8 0, 17 0, 325 andpan. The sized fractions were weighed and the gammaactivity measured on the 4- ionization chamber.

Sub-sieve analyses were conducted on 20 gram portions of the fallout from stations9, 13, 19 and 2 0. The20 grams were wet sieved through a 325 mesh screen. Thematerial remaining on the screen was dried and Ro-tappedas described in the dry sieving above. Material passingthe 325 mesh screen was transferred to a glass cylinder

with a thermally-insulated vacuum jacket. The totalvolume was adjusted to 2000 ml. The cylinder was shakento disperse the sample uniformly and placed in an upright position. As the soil particles settled throughthe vertical column of water, 10 ml aliquots were removedfrom a depth of 10 cm below the original liquid level.

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Successive aliquots were taken at times which excluded 40,30, 20, 10, 3, 3 and 1 micron particles (Reference 4 ) .The aliquots were collected in previously weighed 10 mlvolumetric flasks. The filled flasks were centrifugedand the supernate withdrawn. They were then oven dried toconstant weight and their gamma activity was measured onthe 4-rt ionization chamber.

2.4.2 Gaseous Fission Product Iodine. The radio-iodine from the gas sampler in the field was determinedby oxidizing the iodide in sodium thiosulfate solutionwith nitrous acid, extracting with carbon tetrachloride,reducing back into sodium thiosulfate and precipitatingas silver iodide. The silver iodide precipitate wasplaced in a calibrated geometry and its gamma spectrameasured with the 100-channel pulse height analyzer.Both samples showed only the 0.53 M e v peak characteristicof I 1 3 3 on 8 July at 2100 hours.

I n a concurrent iodine study, ten 20 gram portions offallout from station 19 were placed in petri dishes andexposed to normal air currents and sunlight. One of the20 gram samples was added to a test tube containing 5 0ml of 0.05 M sodium thiosulfate at 2100 houis on 7 July,thus effectively trapping any iodine which would be

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released from the particles. Each day thereafter one ofthe portions was added to a thiosulfate solution. Afterten days on 17 July the radioiodine was extracted from themixture and measured in the following manner: Each testtube was measured initially in the 4- ionization chamber.The slurry of thiosulfate solution and fallout was transferred from the test tube to a bubble column. The iodinewas oxidized with nitrous acid and the iodine transferredto another bubble column containing sodium thiosulfate bydrawing a stream of air through the system. The iodinewas extracted from the second thiosulfate solution by againoxidizing with nitrous acid and extracting into carbontetrachloride. The carbon tetrachloride fractions werethen measured in the 4-n ionization chamber to determinethe radioiodine.

2.4.3 Leaching. The leaching of gamma emitting radionuclides from fallout particles by HCl solutions of pH 1.0and 4.0, distilled water of pH 6.0 and NaOH solution ofpH 10.0 was determined. Two grams of particles from the42, 15 0, and 325 mesh and pan fractions were added to 25ml of solution in 40 ml centrifuge tubes on 7 July. After3 days the tubes were centrifuged, the liquid decantedinto clean tubes and the gamma activity of the solid and

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liquid fractions measured in the 4-n ionization chamber.A duplicate set of samples, also started on 7 July, wastested in 8 days.

2.4.4 Exchange. The desorption of gamma emittingradionuclides from fallout particles and their readsorp-tion on montmorillinite clay and adobe soil was studied.Adobe soil from Camp Parks, Pleasanton, California andcommercial clay from I ndustrial Mineral and ChemicalCompany, Florin, California, were passed through a 325mesh sieve to obtain particles less than 44 micron indiameter. Two grams of active particles from the 42,150 and 325 mesh fractions were mixed with 10 grams ofeach of the soils in test tubes containing 25 ml distilled water on 7 July. After 3 days the components wereseparated by washing the clay or adobe through a 325mesh sieve, and measuring the fractions on the 4-nionization chamber.

2.4.5 Radiochemical Determinations. Sized fractions from dry sieving were analyzed to determine theradiochemical composition of the fallout. Determinationof the radionuclides Sr 9 , Sr 9 0, Y 9 1 , Z r 9 5 , M o 9 9, R u 1 0 3 ,R u 1 0 6 , I 1 3 1 , T e 1 3 2, C s 1 3 6, Cs 1 3? , B a l U , Ce 1* 1, C e 1 ^ ,W were made on the following:

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Station Number Sieve Fraction12 80, pan14 24, 80, pan19 1, 8 0, pan

89 90 91Determination of the radionuclides Sr 7, Sr , Y95and Zr were made on the following:

Station Number Sieve Fraction10 7, 12, 24, 80,

179, 325, pan12 1, 12, 24, 170, 32513 1, 12, 24, 8 0, 170,325, pan14 1, 12, 170, 32519 12, 24, 170, 32520 7, 12, 24, 80, 170,325, pan

The samples were processed in the field and sent toUSNRDL, where they were logged and distributed to threecontracting laboratories:

(1) Tracer lab, Inc.Reactor Monitoring Center2030 Wright AvenueRichmond 3, California(2) Nuclear Science and Engineering Corp.P.O. Box 10901Pittsburgh 36, Pennsylvania(3) Hazelton-Nuclear Science Corp.4062 Fabian WayPalo Alto, California

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TABLE 2.1 STATION LOCATION

S t a t i o nNo.

123456789

101 1121314151617181920

D i s t a n c eFrom GZf t

2 ,7002 ,5002 ,5602 ,8 0 03,3005,2005,0005 ,1005, to o5,8009,300

1 1 ,9 0 01 4 ,2 0 019 ,20017 ,00016 ,10016 ,5001 0 ,0 0 0

9,8009,600

NNNNNNNNN

B e a r i n gd e g r e e s45w22.5W

0 22 .5E45E45w22.5W

0 22 .5E35-5E9wN 1.7E

NN

1 3 .5 E5E

N 7.5WNNNNN

22.5W13-5W15E30E45E

Road

AAAAABBBBBCGG-JD -JDD-FFF

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GROUND.ZE R o imfi^\ \

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CHAPTER 3RESULTS AND DISCUSSION

Extensive use was made of the NRDL 7 04 computer fordata reduction and analysis and random errors are unlikely.However, checks are easily possible through the use of theraw data which are presented in Appendix A.

3.1 FIELD COLLECTIONSAll stations received relatively large deposits.

Stations 1 through 5, along Road A, received such heavydeposits that it was not possible to process them becausethey were more than level full and material had to beremoved to fit the lids. One of the five was hit by alarge rock and received physical damage.

The efficiency ana reliability of the tray collectorwas demonstrated by the very uniform weights (47 8.6,485.1, and 494.9 grams) of debris recovered from thethree collectors at Station 19. It is significant tonote that the gasoline-powered motor generator survivedthe effects of the detonation and was still operatingwhen recovered at 1700 hours on 7 July 1962.

Collectors from Stations 2, 3, and 5 recovered on19 July 1962 were given to Dr. W. E. Martin of the

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Laboratory of Nuclear Medicine and Radiation Biology, UCLA,for biological studies.

3.2 GAMMA ACTI V ITY AND PHYSICAL PROPERTIES OF DEBRISThe measurements reported in this section include

gamma activity, gross mass, and mass and activity distributions as a function of particle size.

3.2.1 Gross Mass and Scintillation Counter Measurements . Al l counting data reported for the low-geometryscintillation counter are for a single geometry, namely,the covered collector on the floor of the counter, 4linches below the crystal. At this distance there waslittle sensitivity (+ 8 percent) to sample position inthe collector. Observed counts are corrected for background, standard, and coincidence. The coincidencecorrection curve is shown in Figure 31 Only the collector from Station 7 was reserved for decay measurement,and the results are presented in Table 31 The resultsfrom the other collectors are presented in Table 3-2.(The raw data is presented in Appendix A, Table A . l ) .Since the decay data from Station 7 started at 4 days,it was necessary to use a representative scintillationdecay curve from Reference 1 (shown in Figure 3 2) to

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correct all collector activities to a common time of 100hours. It must be noted that rather large coincidencecorrections were necessary and that the data from sample7 (also plotted in Figure 32) do not fit well on thestandard curve. The gamma activity measurements madewith the scintillation counter do not have as much reliability as those made with the 4-it ionization chamber,and therefore specific activity measurements in thefollowing section are more meaningful.

3.2.2 Gamma Decay Rates by h-it Ionization Chamber.The decay rates measured in the k -n ionization chamberare listed in Table 33 All readings were correctedfor background and normalized to a standard response of560 x 10 y ma for 100 micrograms of Ra, to enable directcomparison with fission product response listed in Reference 2. The last column is the computed activity at100 hours, obtained by applying the decay correctionfactor from the decay curve from Station 19 shown inFigure 33 Thus, the constancy of the numbers in thelast column is a measure of the goodness-of-fit of theindicated sample to decay from Station 19. The secondcolumn indicates the particle size; the absence of avalue in this column means that the values represent a

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gross sample. The letter "W" after the micron size showsthat the sample was wet sieved. Raw data are given inAppendix A, Table A. 2.

An interesting comparison is shown by the second curveplotted in Figure 33 This is a computed decay curve fromfission products and induced radioactivities produced bythe Sedan device. The calculations were in terms of doserate so the results should be comparable to the U-rtresults since both are gamma ionization measurements. Thetwo curves were normalized at 100 hours and the nearly-identical shape clearly indicates that the computed values

were well within the 20 percent which was predicted asa probable error.

3.2.3 Mass and Activity Distribution by ParticleSize. The mass of debris collected was adequate for goodmeasurements and the gamma activity was well within therange of the h- n ionization chamber. The Ro-tap sieveanalysis for sizing particles, and water sedimentationfor determining sub-sieve particle size distribution provided the desired results.

Memorandum UOHC 63-3, of February 1963, from Gary H.Higgins.

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The results showing mass and activity distributions ofthe debris are reported in Table 3^ Inspection of theresults indicates that the activity is nearly proportionalto mass, that is, the specific activity is nearly constantfor all particle size fractions. Under microscopic examination the particles appeared to be unaltered and noglassy spheres from melted material were observed. Ifthe radionuclides were adsorbed on the surface of unalteredparticles, more activity should be distributed on thesmall particles with the larger surface area per gram.It would seem that in this case the activity is distributed more nearly as a function of the particle volume.

3-3 V OI ATH I TT OF FISSION PRODUCT IODINERadioiodine was found in milk at locations far re

moved from the Nevada Test Site during the 1962 tests.The lack of pertinent data concerning the release ofradioiodine from debris, prompted the design and execution of these experiments.

Recovery of the gas sampler at Station 19 was initially planned for H + 2, but this was not possible becauseof the radiological situation. An early recovery wouldhave permitted a determination of the iodine in the 134

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and 135 mass chains, both of which have a large fractionof their yield directly as iodine.

The data in Table 35 show that gaseous radioiodinewas present in the air during the contaminating event,and that some radioiodine was released as a gas from thedebris collected in the funnel. Assuming the same air

133flow in both sample streams, the measured yield of I ^ Jfrom the debris can be found by sub-feracting 95 photons/second and dividing by 95*8. The resulting I.96 photons/second from 283 photons/second/gram at zero time seemssmall compared to the total amount which should be associatedwith the debris. This total can be estimated from h-n ionization readings with the aid of Reference 5 and Reference6. At ik.k days (minimum induced activities) the debrisfrom Station 19 measured 7*5 x 10 ma/gram, and Reference

y . -ill . ll5 shows O.OO67 x 10 ma/10 fissions. Thus the debris12from Station 19 had approximately 1.1 x 10 fissions/gram. Since the experiment was stopped at recovery(1700 hours on 7 July)* this is a good time to compare themeasured and computed yields. Reference 6 shows 0.0021d/s of I 33/K > fissions at 1.29 days (1700 hours on 7July), and 1.12 x 1 0 1 2 x 0.002l/l0^ = 2.35 x 10 5 d/s/g= 2.35 x 10 photons/second/gram at 1.29 days. The

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absence of I peaks in the gamma spectra of these twosamples can be explained by the time lapse (28 hours)between sample recovery and spectra analysis which was

132more than 10 half-lives for I J .Iodine loss by air exposure over a 10 day period is

reported in Table 3-6. The progressive decrease in theobserved iodine/total fraction with time indicates a lossof iodine during the period. Reference 5 shows that at alldays the radioisotopes of iodine contribute 25.0 percentof the gamma radiation (by k -% ionization chamber) from

235normal U thermal fission products. Dividing the observed iodine/total fraction by the expected fraction(0.25) yields the percentage of the theoretical iodineactually recovered. The most apparent reason for the lowinitial percent (33*3 percent) was the inability of theanalytical procedure to remove iodine which might havebeen trapped within the insoluble particles. I n addition,the iodine may have been depleted from the outset dueto fractionation in the fallout formation process.

The results are shown plotted in Figure 3.k. Thestraight line is characteristic of a zero order reaction,which indicates that the mechanism for rate of releaseis one of diffusion.

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It is emphasized that these results were obtained byan analytical procedure which was developed in the field.The iodine recovery is not known for these methods, norwas the purity of the iodine product in the second experiment, since no spectra or decays were obtained. However,

spectra from the first experiment (Figure 35) showed avery high radioiodine purity.

3. k LEACHING OF GAMMA EMITTERS FROM DEBRIS TO VARIOUSSOLUTIONSThe leaching of radionuclides by solutions of pH 1.0,

k.O, 6.0, and 10.0 is shown in Tables 3.7 and 3.8 . Theacidicity or basicity of the solution apparently haslittle effect on the leaching result. Small particleswith their much greater surface area do leach a largerfraction of the radionuclides than large particles. Acomparison of Table 3.7 with Table 3.8 shows littleincreased leaching in the additional five days of contact.Unfolding of the gamma spectra (Figure 36) which weretaken of the two fractions may determine if radionuclideswere selectively leached into solution.

3.5 EXCHANGE OF GAMMA EMITTERS FROM DEBRIS TO CIAYAND ADOBEThe ion exchange studies showed that the radi^nuclideo

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did exchange from fallout particles to materials with ahigh adsorptive capacity. Table 3*9 shows that commercialclay was somewhat more effective than adobe soil and thatthe smaller particles with large surface area gave up agreater fraction of their radionuclides than did tne

large particles.3.6 PULSE HEI GHT DISTRI BUTIONS

The similarity of the radiochemical composition ofdebris from different locations is evidenced by the pulseheight distributions shown in Figures 3*7* 38 and 39The pulse height distribution of sized fraction of debrisare shown in Figures 31> 3 - H and 312. Again thesimilarity of the radiochemical composition is apparent.Pulse hei. it distribution of the solid and liquid fractions from leaching studies are shown in Figure 3-6.The radiochemical purity of the iodine precipitate fromthe field gas samples is shown in Figure 3*5-

3.7 RADIOCHEMISTRYResults of radiochemical analyses are reported in

Table 3>10. Equivalent fissions per gram were calculatedfor each radionuclide using the raw data shown in AppendixA, Table A. h and the fission yields appropriate to this

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detonation. The method is described in Reference 7Inspection of Table 3*10 indicates little difference

99in the results for equivalent fissions between Mo and

95 185Zr . The capture to fission ratio for W was higherfor particles in the pan fraction than for large particles.

Certain discrepancies in the data are apparent suchas the Sr y/S r ratio for 8 0 mesh particles from Station10. Large differences are evident in the results for thepan fraction from Station 12 that are reported by thethree contracting laboratories. Many of these discrepancies can no doubt be resolved by further analysis of thedata.

While radiochemical fractionation was not observedby the gamma decay measurements nor by the pulse heightspectra, perhaps the radiochemical data will provide amore sensitive test. R-values as discussed in Reference 8are useful indices of fractionation. The R-value is defined as the ratio of the number of atoms of a radionuclide to the number of atoms of a reference radionuclide in a debris sample divided by the same ratio for235thermal neutron fission of U . Enrichment or depletionare manifested by positive or negative deviations fromthe characteristic value.

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3.8 SIGNIFICANCE OF DATANo further discussion of the results are possible at

this time. I t is evident however, that a great deal ofinformation is contained in these data, the analysis ofwhich can serve as basic input for many future studies.

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TABLE 3.1 GAMMA DECAY RATES BY SCINTILLATION COUNTER

SampleNumber

77777777777

Agedays

4.21409.036010.000011.357012.352013.6320l4.208014.995018.244019.109020.1590

CorrectedActivityc/m

7316537.3918468.3111225.2811743.976359.2358356.2031223.1896451.1664244.1518397.1536483.

Activityat 100 Hrc/m

7436266.12233624.12158404.12129882.4471680.

II790854.IO616326.10531781.II290360.IO958602.11899217.

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TABLE 3-2 GAMMA ACTIVI TY AND GROSS MASS OF DEBRIS COLLECTED

Sample Activity at Empty Weight Activity Mass SpecificNumber 100 hr Collector Recovered Concentration Concentration ActivityActivityat 100 hr

6 SE8 SE9 SE10 SE11 SE12 SE13 SE14 SE15 SE16 SE17 SE18 SE19 SE20 SE

c/ m9565100 .641497251910321646234 .1864910 .-664817 ._346266 .1356415 .633211 .966452 .1487012 .755423 .

c/m51000 .30474 .4286811198 .2 0 4 9 1 .- 9305 .- 0 .26672 .0 .2 1 6 1 1 .4 5 5 6 .4 0 5 7 .

grams4 2 2 6 . 73 2 5 4 . 32 5 4 3 . 91 2 5 6 . 56 2 8 . 04 7 6 . 62 8 6 . 34 4 . 85 5 . 32 2 9 . 01 2 0 . 03 9 6 . 8

4 9 5 . 03 6 3 . 2

c/m/sq f t2391275 .1603743 .1297758 .411559-4 6 6 2 2 8 .- 166204 .- 86567 .3 3 9 1 0 4 .158303 .2 4 1 6 3 6 .371753 .188856 .

g r a m s / s q f tI O56 .78 1 3 . 6636.O3 1 4 . 1157- 0I I 8 . 97 1 . 61 1 . 21 3 . 85 7 - 23 0 . 09 9 . 2

1 2 3 . 89 0 . 8

c/m/gram.2263-1973.2040.13102969.2321627259285276243530022079

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TABLE 3-3 Gamma decay rates by ^-pi ionization chamber

\MPLENUMBER

6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO6 AO

8 AC8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO

SIZE AGE(MICRONS) (DAYS)

4*9570525005*94806*88907.87509*05209*188010.971012.966016.966019*886023.012024.969028*043032*119034*9980

38.951041*948045.929048.910056*113062*016076*134084*040091.0500105.9900150.9810227.0610

4*95805.25205.94906*89007*87509*05309*188010*971012*966016.966019.886023.013024.969028.043032.1200

34.998038.952041*949045.930048.9110

CORRECTED ACTIVITY(MA>

0.5283E-060.4943E-060.4021E-060.3256E-060.2738E-060.2295E-060.2212E-060.1852E-060.1501E-060.1167E-060.9833E-070.8408E-070.7740E-070.7638E-070.6037E-070.5550E-070.5004E-070.4641E-070.4264E-070.4002E-070.3516E-070.3251E-070.2623E-070.2457E-070.2297E-070.1989E-070.1370E-070.8484E-08

0.3796E-060.3475E-060.2847E-060.2170E-060.1902E-060. 1610E-060.1543E-060.1292E-060,1041E-060.7781E-070.6574E-070.5650E-070.5190E-070.4462E-070.4014E-070.3699E-070.3352E-070.3110E-070.2844E-070*2644E-07

ACTIVITY AT 100 HR(MA)

0.7001E-060.7272E-060.7306E-060.7283E-060.7276E-060.7250E-060.7110E-060.7384E-060.7063E-060.7212E-060.7121E-060.7100E--060.7156E-060.7903E-060.7075E-060.6992E-060.6962E-060.6925E-0606953E-060.6975E-060.7082E-060.7268E-060.6994E-060.7172E-060.7252E-060.7323E-060.7250F-060.6905E-06

0.5033E-060.5117E-060.5175E-060.4854E-060.5055E-060.5086E-060.4961E-060.5152E-060.4900E-060.4R09E-060.4760E-060.4771E-060.4799E-060.4616E-060.4704E-0604660E-060.4664E-060.4641E-060.4638E-060.4607E-06

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TABLE 3-3 (Continued) Gamma decay r a tes by 4-p i ioni za t io n chamber

SAMPLE NUMBER

8 AO8 AO8 AO8 AO8 AO8 AO8 AO8 AO

10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO10 AO

12 AO12 AO12 AO12 AO12 AO12 AO12 AO12 AO12 AO12 AO12 AO

S I Z E AGE( M I C R O N S ) ( D A Y S )

5 6 . 1 1 4 06 2 . 0 1 6 07 6 . 1 3 4 08 4 . 0 4 2 09 1 . 0 5 0 0

1 0 5 . 9 9 0 01 5 0 . 9 8 1 02 2 7 . 0 6 1 0

5.25305.95106.89107.87509.05309.1880

1 0 . 9 7 1 012.966016.96601 9 . 8 8 6 02 3 . 0 1 4 02 4 . 9 6 9 02 8 . 0 4 3 03 2 . 1 2 0 03 4 . 9 9 9 03 8 . 9 5 9 04 1 . 9 4 9 04 5 . 9 3 1 04 8 . 9 1 1 05 6 . 1 1 5 06 2 . 0 1 7 07 6 . 1 3 5 08 4 . 0 4 2 09 1 . 0 5 0 01 0 5 . 9 9 0 01 5 0 . 9 8 1 02 2 7 . 0 6 3 0

1 6 . 9 6 6 01 9 . 8 8 6 02 3 * 0 1 5 02 4 * 9 6 9 02 8 * 0 4 3 03 2 . 1 2 2 03 5 * 0 0 0 03 8 * 9 6 0 04 1 * 9 5 1 04 5 * 9 3 2 04 8 * 9 1 3 0

C O R R E C T ED A C T I V I T Y(MA)

0.2322E-070.2156E-070.1752E-070,1638E-070.1520E-070.1371E-070.9036E-080.5701E-08

0*3984E-060.3225E-060.2588E-060.2128E-060.1794E-060.1735E-060,1418E-060,1150E-060.R576E-070.7159E-070.6168E-070.5650E-070.4869E-070.4338E-070.4024E-070.3634E-070.3352E-070.3021E-070.2849E-070.2528E-070.2324E-070.1918E-070.1P05E-070 . 1 6 4 5 E - 0 70,1471E-070.1031E-070.6472E-08

0.8576E-070.7059E-070.6001E-070.5441E-070.4638E-070.4540E-070.3334E-070.3352E-070.3030E-070.2740E-070.2602E-07


0.4677E-060.4820E-060.4671E-060.4782E-060.4798E-060.5046E-060.4781E-060.4640E-06

0.5868E-060.5863E-060.5789E-060.5654E-060.5667E-060.5579E-060.5652E-060.5411E-060.5300E-060.5184E-060.5209E-060.5224E-060.5038E-060.5083E-060.5069E-060.5057E-060.5001E-060.4926E-060.4966E-060.5C92E-060.5197E-060.5114E-060.5270E-060.5194E-060.5415E-060.5455E-060.5268F-06

05300E-060.5111E-060.5068E-060.5031E-060.4799E-060.5321E-060.4200E-060.4665E-060.4521E-060.4468E-060.4536E-06

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TABLE 3 - 3 ( C o n t in u e d ) Gamma d e c a y r a t e s b y 4 - p i i o n i z a t i o n c h a mb e r

SAMPLE NUMBER

1212121212121212

131313131313131313131313131313131313131313131313131313

1515151515IS151515

AOAOAOAOAOAOAOAO

AOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAO

AOAOAOAOAOAOAOAOAO15 AO15 AO


56.116062.018076.1360S4.044091.0500105.9900150.9810227.0660

2.25405.96106.89307.87509.05409.188010.971012.966016.966019.889023.O15024.96902^.043032.12203=5.00103^.961041.952045.932"4.914056.116062.020076.1370B4.044091 tO^OO105.990"150.981C'27.06704.95905.25505.96506.89307.O7509.05409.1 8 8"10.971"12.066"16.96901Q.B890

CORRECTED ACTIVITY(MA)

0.2224E-070.2004E-070.1628E-070.1471E-070. 1394E-070.1220E-070.8188E-080.4963E-0R

i,5045E-060.4105E-060.334 0E-OS0.2822E-060.2354E-060.2270E-060.1877E-050* 158 5E-060, 1234E-0S0.9833E-070.8492E-070.8074E-07C.7008E-070.6280E-070.5769F-070.5205E-070.4802E-070.4385E-070.4002E-O70.36?4g_070.3318E-070.270 6E-07'1.2474E-070.2314E-07o,?056E-070 1406E -07O.P484E-0P

0.8669E-060.P312E-060.6746F-060.5496E-06n,4S94F-060.3R00F-060.380 0E-060.3006E-060.2462E-06r'.ir?5E-C60.150PE-06


0.4478E-060.4482E-060.4340E-060.4294E-060.4402E-060.4492E-060.4332E-060.4040E-06

0.1874E-060.7482E-060,7475^-060.7498E-060.7437E-060.7299E-060.74R4E-060.7456F-060.7625E-060.7122E-060.7172E-060.7465E-060.7250E-060.7360E-060.726PE-060.7244E~060.7166E-060.7150E-060.6976F-060.7298E-06^7419E-060.7215E-060.7221E-060.730^E-060.7569E-060.7441F-060.6906E-06

n, J i=;nF_050,1225E-0Cn 1?"* 1^-050. 123np r-05o,1221E-050.1201E-050.1222E-05o, i ignE-o*;0, 1 15OF-050.1 135 E-050.1037F-05

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TABLE 3.3 (Continued) Gamma decay rates b^ U-pi ionization chamber

SAMPLE NUMBER

15 AO15 AO15 AO15 AO15 AO15 AO15 AO15 AO15 AO15 AO15 AO15 AO15 AO15 AO15 AO15 AO15 AO

16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO16 AO

17 AO


23*016024.969028.043032.123035.00603R.962041.952045.93304R.914056.117062.025076.137084.045091.0500105.9900150.9810227.0670

4.96005.25505.96506.89407.87809.05509.188010.971012.966016.969019.889023.016024.969028.043032.124035.006038.962041.953045.933048.914056.117062.026076.138084.046091.0500105.9900150.9810227.0680

4.9610


0.1317E-060,1209E-060.9946E-070.9031E-070.8488E-070.7703E-070.705RE-070.6430E-070.607RE-070.5246E-070.4834E-070.3552E-070.3728E-070.3400E-070.2959E-070.2049E-070.1242F-07

0.8421E-060.8100E-060.6536F-060.5329E-060.4443E-060.3691E-060.3591E-060.2905E-060.2337E-060,I752E-060.1443E-060,1242E-060.1150E-060.9331E-070.8869E-070.7920E-070.7018E-070.6454E-070,=iP29E-070.5485E-070.4752E-070.4303E-070.3536E-070.3226E-070.2982E-070.2599E-070.1R37F-070.M25E-07

0.8256E-06

ACTIVITY AT 100(MA)

0, 1 113E-050, 1 117E-050.1029E-050,1058E-050.1070E-050,1072E-050,1053E-050,1049E-050,1059E-050,1057E-050.10R1E-050.9471E-060,10SPE-050.1074E-050,10R9E-050,1084E-050,1011E-05

0,1117E-050,1194E-050,11Q3E-C50.1193E-050.1181E-050,1166E-050,1154E-050.1158E-050,1100F-050,1083E-050,1045E-050,1049E-050.1063F-050.9653E-060.1040E-050.9979E-060.976PE-060.9631E-060.9505E-06C.9560E-060.9570E-060.9623E-060.9427E-060.9417E-060.9416E-060.9569E-060.9720E-060.9I58E-06

0.1096E-05

HR

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TABLE 3-3 (Continued) Gamma decay r a tes by 4-pi ioniza ti on chamber

SAMPLE NUMBER

1717171717171717171717171717171717171717171717171717

AOAOAOAOAOAOAOAOAOAO*0AOAOAOAOAOAOAOAOAOAOAOAOAOAOAO

17 AO

18181818181818IS1818181818t-a1818181818ia18

AOAOAOAOAOAOAOAOAOAOAOAOAO>AOAOAOAOAOAOAO

S I ZE AGE(MICRONS). (DAYS)

5.25605.96706.89507.87809.05509*188010.974012.966016.969019.889023.017024.969028.043032.124035.007038.9630

41.954045*934048*915056*118062*027076*138084.047091.0500105.9900150.9810227.0680

4.96205.25705*96806*89507*87809I055C9*188010*974012*966016.969019.889023*017024*9fyO28*043032.125035*007038.964041*954045.935048*9-15056.1180


0.7S03E-060.6326E-060.5179E-060.4326E-060.3591E-060.3507E-060.2838E-060.2295E-060.1693E-060, 1418E-060.1225E-060.1125E-060.9177E-070,8060E.070.7692E-070.6817E-070.6253E-070.5668E-070.5320E-070.4645E-070.4177E-070.3436E-070.3151E-070.2899E-070.2516E-070.1752E-070.105SE-07

0.3961E-060.3713E-060.3015E-060.2437E-060.2069E-060.173BE-060.1693E-060.1334E-060.1150E-060.8993E-070.7284E-070.6235E-070.5734E-070.4869E-070.4297E-070.3983E-070.3553E-070.3271E-070.2956E-070.2767E-070.2364E-07


0.11S0E-050.1155E-050.H59E-050.1150E-050.1135E-050.1128E-050.1132E-050.1080E-050.1047E-050.1027E-050,1035E-050,1040E-050.9494E-0609447E~060.9693E-060.9488E-060.9330E-060.9244E-060.9273E-060.9355E-060.9341E-060,9162E~060.9198E-060.9152E-060.9262E-0609271E-060.8612E-06

0.52S9E-060.5476E-0605505E-060.5457E-060.5502E-060.5484E-060.5444E-060.5320E-060.5411E-060.5559E-060.5276E-060.5266E-060.5301E-060.5038E-060.5036E-0605019E-060.4946E-060.4882E-060.4822E-0604823E-060.4760E-06

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TABLE 3 . 3 ( C o n t i n u e d ) Ganmia d e c a y r a t e s b y ^ - p i i o n i z a t i o n c h a m b er

SAMPLE NUMBER

IS1818IS181818

191919f91919191919191919191919191919191919*1919191919

AOAOAOAOAOAOAO

AOAOAOAOACAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAO19 AO

191919191919191919191919

AOAOAOAOAOAOAOAOAOAOAOAO

SIZEMICRONS)

283028302830283028302830283028302830283028302830

AGE(DAYS >

62*027076*139084*O48091*0500105*9900150.9810227'lO690

5*25805*96906*89507*87809*05609.188010.974012.966016*969019*889023*018024*97 5028.043032*125035*008038*964041*95 5045*936048*916056.119062.028076.139084.048091*0500105.9900150.9810227.0700

1*46501.58302.02902.40902.89603.27104*94805.99R06*91409.177010.980012.9310


0.2155E-070.1752E-070.1638E-070.1478E-0701346E-070.9036E-080.5634E-08

0.4680E-060.3770E-060.3047E-060.2546E-060.2103E-060.2044E-060.1693E-060.I376E-060.1067E-060.8496E-070.7556E-070.6946E-070.6062E-070.5390E-070.4982E-070.4520E-070.4158E-070.3823E-070.3673E-070.3187E-070.2914E-070.2416E-070.2265E-070.2063E-070.1S72E-070.1285E-070.8065E-08

0.2151E-060.1979E-060.1444E-060.1207E-060.R344E-070.6926E-070.3395E-070.2541E-070.2056E-070.1463E-070.1245E-070.1036E-07

A C T I V I T Y A T 1 0 0 HR( MA )

0 . 4 8 2 1 E - 0 60 . 4 6 T 2 E - 0 60 . 4 7 8 2 E - 0 60 * 4 6 6 6 E - 0 60 . 4 9 S 4 E - 0 60 . 4 7 8 1 E - 0 60 . 4 5 8 6 E - 0 6

0 . 6 9 0 5 E - 0 60 . 6 8 8 4 E - 0 60 . 6 8 2 3 E - 0 60 . 6 7 6 8 E - 0 60 . 6 6 4 7 E - 0 60 . 6 5 7 3 E - 0 60 . 6 7 5 4 E - 0 60 . 6 4 7 3 E - 0 60 . 6 5 9 3 E - 0 60 6 1 5 3 E - 0 60 6 3 8 2 E "0 60 * 6 4 2 4 E - 0 60 . 6 2 7 1 E - 0 60 6 3 l 7 E - 0 60 6 2 7 7 E - 0 60 * 6 2 9 2 E - 0 60 * 6 2 0 4 E - 0 60 . 6 2 3 5 E - 0 60 . 6 4 0 2 E - 0 60 6 4 1 9 E - 0 60 . 6 5 1 6 E - 0 60 . 6 4 4 1 E - 0 60 * 6 6 1 2 E - 0 60 , 6 5 1 3 E - 0 60 . 6 8 9 2 E - 0 60 6 8 0 2 E - 0 60 . 6 5 6 5 E - 0 6

0.4725E-070.4721E-0704644E-070.4952E-070.4454E-070.4481E-070.4484E-070.4674E-070.4619E-070.4696E-070.4970E-070.4862E-07

kz

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TABLE 3.3 (Continued) Gamma decay rates by It-pi ionization chamber

SAMPLE NUMBER

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO

19 AO

SIZE(MICRONS)

28302830283028302830283028302830283028302830283028302830283028302830

14101410141014101410141014101410141014101410141014101410141014101410141014101410141014101410141014101410141014101410

7 10

AGE(DAYS)

16.977019.896023*005024*959032*127034*980038.966041.960045.939048.945056.199062.04 3076.122084.0140106.0000150.9810227.1360

1.46501.58302.02902.40902.89903.27204.94906.00006.91409.177010.9P0012.931016.977019.896023.006024.959032.128034.982038.968041.962045.940048.948056.202062.045076.12208^.0150106.0000150.9O1022^.1370

1.4650

COftRECTED ACTI V I TY(MA)

0.8442E-0R0.7397E-080.6595E-080,5976E>-080.4775E-080.4545E-080,4342E-0R0.4058E-080.3733F-080.3624E-0803l71E-080.2947E-080.2306E-080.2131E-080.2140E-070.1315E-080.5851E-09

0.4675E-060.4262E-060.3167E-060.2504E-060.1820E-060,1581E-060.7483E-070.5525E-070.44ROE-070.3067E-070.2574E-070.2140E-070.16P0R-070.1471E-070.1321E-070.124SE-070.1036E-070.9820E-0R0.8765F-080.8603E-080.7791E-080.7247E-080.6753E-0P0.5979E-0R0.5044E-080.4S90E-0R0.4012E-0R0.2R0OE-O80.148PE-0R

0.4649E-06

ACTI V ITY AT 100 HR(MA)

0.5221E-070.5359E-0705 567E-070.5523E-070.5596E-070.5723E-070.6044E-070.6056E-0706089E-0706320E-0706396E-070.6593E-070.6148E-070.6219E-070*7878E-060.6959E-070.4765E-07

0.1027E-060.1017E-060.1019E-060.1027E-060.9730E-070.1023E-0609889E-070.1017E-060.1007E-060.9848E-070.1027E-060.1004E-060,1039E-060.1066E-060.1 115E-060.1151E-060.1214E-060.1237E-060,1220E-060.12R4E-060.I271E-060.1264E-060.1362E-060.1337E-060.1345E-060.1427E-060.1477E-060, 1482E-060,1212E-06

0.1021E-06

43

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TABLE 3.3 (Continued) Gamma decay r a tes by k-pi ionization chamber

SAMPLE NUMBER

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AC19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 4019 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO

SIZEMICRONS)

710710710710710710710710710710710710710710T10710710710710710710710710710710710710710

177177177177177177177177177177177177177177177177177177177177

AGE(DAYS)

1.58302.02902.40902.89903.27304.95006*00006*91409*177010*980012*931016.977019.896023.006024.962032.129034.982038.969041.963045.943048.950056.206062.046076.123084.0160106.0000150.9810227.1380

1.46501*58302*03202*40902*89903*27604*95006*00106.91409.177010.980012.931016.977019*896023*00702^*962032*150034*982038*971041.9670


0.4262E-060.309PE-060.2504E-060. 1R63E-060. 1597E-060.750PE-070.5466E-070.4396E-070.2967E-070.2457E-070.2056E-070,1580E-070.1371E-070,1229E-070.1137E-070.9387E-080.8603E-0R0.8197E-08C.7791E-0S0.7264E-080.7000E-OP0.6176E-08O.S600E-080.4712E-080./I472E-080.367RE-080.2673E-080.1421E-08

0.3943E-060.3659E-060.2659E-060.2115E-060,1603E-060.1357E-060.6451E-070.4689E-070,3811E-070.2566E-070.2165E-070,1805E-070.1429E-070,1220E-070.1103E-070.1137E-070.8416E-080.7791E-080.7467E-080.7020E-08


0.1017E-060.9964E-070*1027E-060.9962E-070,1034E-060.9925E-070.1006E-060.9877E-070.9526E-070.9807E-070.9646E-070.9769E-070.9931E-070.1037E-060,1051E-060.1100E-06O.1083E-060.1141E-060.1163E-060,1185E-060.1221E-060.1246E-060.1253E-060.1256F-060.1305E-060.1354E-060.1414E-060.1157E-06

0.8662E-0708730E-070.8568E-070.8674E-070.8570E-070.8798E-070.852RE-070.R632E-070.8563E-070.8238E-070.8640E-070.8470E-070.8839E-070.8841E-070.9314E-070.1051E-060.9870E-070.9812E-070.1039E-060.1048E-06

hk

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TABLE 3.3 (Co ntinue d) Gamma decay r a te s by 4- pl io ni za ti on chamber

SAMPLE NUMBER

1919191919191919

AOAOAOAOAOAOAOAO19 AO

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AOre AO19 AO19 AO19 AO

19 AO19 AO19 AO19 AO19 AT>19 AO19 AO19 AO

S IZE(MICRONS)

17 717 717 717 717 717 717 717 717 7

12412 412412412412412412412412412412412412412412412412412412412412-+12412412412*124124124

8 C8 88 88 88 88 88 88 8

AGE(DAYS)

4 5*94 504 8*9 50056.20 8062.047076.124084.0190106*0000150.9810227.1390

1.46801.58602.03202*40902*89903*27804.95106.00206.91409.180010.980012.931016*977019*896023*008024*962032*151034*98303 8 * 9 7 5 041*9690

4 5.94 704 8.9 52056.211062*048076*12 5084O200106*000C150.9810227.1400

ll4801*58602*03502*40902*39903*28004*95306*0050


0.6452E-080.6218E-080.5518E-0S0.4884E-080.4215E-080.3883E-080.3343E-080.2333E-080.1296E-08

0.2263E-060.2091E-060.1530E-060.12SOE-060.9082E-070.7726E-070.3766E-070.2725E-070.2222E-070.1546E-070.1262E-070.1011E-070.8442E-080.7146E-080.6168E-080.5767E-080.4370E-0R0.10S5E-080.3977E-080.3896E-080.3490E-080.3459E-080.2981E-080.2737E-080.2348E-080.221SE-080.1755E-080.I230E-080.7940E-09

0.3O30E-060.2771E-060.2047E-060.1639E-060.1238E-060.1037E-060 50 8E-0 70.3728E-07

ACTI V I TY AT 100 HR(MA)

01052E-060.1085E-060*lll3E-0601093E-060.1123E-060.1133E-060.1231E-060*1235E-0601055E-06

04982E-070.4999E-070.4931E-0705129E-0704856E-070,5016E-0704981E-070.5017E-0704995E-0704966E-070.5037E-070.4745E-070.5221E-070.5178E-070.5208E-07O.S331E-070.5125E-0701329E-070 5 53 7E-0 70.5815E-070.5693E-070.6034E-070.6015E-070.6I22E-0706259E-070.6463E-070.6462E-070.6510E-070.6467E-07

0.6670E-0706626E-0706609E~0706724E-0706620E-070.6736E-070 8 733E-0 706869E-07

45

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TABLE 3 .3 (Co ntin ued ) deca y ra te s by l ) -p i i o n i za t i o n cha m ber

SwMHLe NUMBER

1 9 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO

19 AO19 AO19 AO19 AO19 AO19 AO19 AO1 9 AOV9 AO19 AO19 AO19 AO19 AO19 AC19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO1-9 AO19 AO

S I Z E(MICRONS)

8 88 88 88 88 88 88 88 88 88 88 88 88 88 88 88 88 88 88 88 88 8

444444444444444444444444444444444444444444444444444444

AGE(DAYS)

69t709*180010*983012*931016*977019*896023i0O9024*962032*133034.98303 8 .9 7 7 041*971045*950048*954056*213062*0500

7 6*12 5 084*0210106*0000150*9810227*1410

1*46801*58*02*03502*40902*90203*28204*95606*OO306*91709*180010.983012.931016*977019*896023*0100

24*962032.134034.98403 8 .9 7 8 041*972045*95104 8 *9 5 105 6*21 5 062*051076.126084*0220106.0210

CORRECTED ACTIVITY(MA>

0*3017E-070.2048E-070.1T22E-070.1387E-070.1095E-0708860E-080.8024E-080.7690E-080.5827E-080.5641E-080.5194E-080.4870E-080.4464E-080.4324E-080.3788E-080.3326E-080.2638E-080.2633E-080.2I73E-080.1570E-080.8191E-09

0.1034E-0509043E'-060.7104E-060.5744E-060. 438.1 E-060.3277E-060.1814E-060.1334E-060.1067E-060.7380E-070.5984E-070.4965E-070.3728E-070.3143E-070.2741E-070.2541E-070.2015E-070.1842E-070.1712E-070, 1591E-070.1469E-070.1408E-070.1211E-070.1145E-070.9690E-080.8901E-080.7355E-08


0 . 6 7 S 3 E - 0 70 . 6 5 7 7 E - 0 70 , 6 S 7 4 E - 0 70 . 6 5 0 9 E - 0 70 . 6 T 7 1 E - 0 70 . 6 4 1 9 E - 0 70 . 6 7 7 5 E - 0 70 7 1 0 7 E - 0 70 * 6 8 3 0 E - 0 70 . 7 1 0 3 E - 0 70 . 7 2 3 2 E - 0 70 . 7 2 6 9 E - 0 70 . 7 2 8 2 E - 0 70 . 7 5 4 2 E - 0 70 . 7 6 4 4 E - 0 70 . 7 4 4 1 E - 0 70 . 7 0 3 3 E - 0 70 . 7 6 8 3 E - 0 70 . 8 0 0 1 E - 0 70 8 3 0 5 E - 0 70 . 6 6 T 1 E - 0 7

0 * 2 2 7 5 E - 0 60 . 2 1 6 2 E - 0 60 2 2 9 4 E - 0 60 . 2 3 5 6 E - 0 60 . 2 3 4 6 E - 0 60 . 2 1 3 1 E - 0 60 . 2 4 0 3 E - 0 60 . 2 4 5 7 E - 0 60 2 3 9 7 E - 0 60 . 2 3 7 0 E - 0 60 . 2 3 8 9 E - 0 60 . 2 3 2 9 E - 0 60 . 2 3 0 5 E - 0 60 2 2 7 7 E - 0 60 . 2 3 1 5 E - 0 60 . 2 3 4 9 E - 0 60 . 2 3 6 2 E - 0 60 . 2 3 2 0 E - 0 60 2 3 8 4 E - 0 60 . 2 3 7 5 E - 0 60 . 2 3 9 7 E - 0 60 . 2 4 5 7 E - 0 60 . 2 4 4 3 E - 0 60 , 2 5 6 2 E - 0 60 . 2 5 8 3 E - 0 60 . 2 5 9 8 E - 0 60 . 2 7 0 9 E - 0 6

k6

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TABLE 3.3 (Co ntinue d) Gamma decay r a te s by 4- pi i o n iz at io n chamber

SAMPLE" NUMBER

19191919191919191919191919191919191919191919191919191919191919

191919191919191919191919191919

AOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAO

AOAOAOAOAOAOAOAOAOAOAOAOAOAOAO

STZE(MICRONS)

4444

PANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPANPAN

2830W2830W2830W2830W2830W2830W2830W2830W2830W2830W2830W2830W2830W2830W2830W

AGE(DAYS)

150.9810227.1430

1.46801.58602*03502*40902*90203.28504.95606.00506.91709.180010.983012.931016.980019.900023.010024*967032*135034.98 5038.979041.972045.952048.952056.216062.052076.133084.0360

106.0450151.0100227.1500

3.18805.05705.97506.94007.88609.07309.191010*989012*994016*980019*904022*984024.972032.136034.98 80


0.5218E-080.2925E-0S

0.3230E-050.2972E-0502214E-050.1832E-050.1415E-050.1240E-050.6191E-060.4594E-060.3716E-060.2461E-060.2003E-060.1652E-060.1234E-060.9996E-070.8492E-070.7865E-070.5916E-070.5405E-070.4837E-070.4431E-070.4026E-070.3772E-070.3269E-070.2998E-070.2446E-070.2244E-070. 1805E-070.1285E-070.7815E-08

0.9833E-070.4438E-070.3419E-070.2725E-070.2307E-070.1956E-070, 1889E-070, 1596E-070.1346E-070, 1095E-070.9278E-080.8442E-0P0.8024E-080,62?2E-080.6168E-0R

A C T I V I T Y A T( M A ) 100 HR

0 . 2 7 6 1 E - 0 60 . 2 3 8 3 E - 0 60 . 7 1 1 2 E - 0 60 . 7 1 0 7 E - 0 6O 7 1 4 8 E - 0 60 . 7 5 1 4 E - 0 60 . 7 5 7 7 E - 0 60 . 8 0 7 5 E - 0 60 . R 2 0 2 E - 0 60 . 8 4 6 5 E - 0 60 , 8 3 5 3 E - 0 60 . 7 9 0 6 E - 0 60 7 9 9 5 E - 0 f0 7 7 4 8 E - 0 G0 . 7 6 3 1 E - 0 60 7 2 4 4 E - 0 60 . 7 I 7 0 E - 0 60 . 7 2 7 1 E - 0 60 . 6 9 3 5 E - 0 60 6 8 0 7 E - 0 60 , 6 7 3 5 E - 0 60 . 6 6 1 5 E - 0 60 . 6 5 6 8 E - 0 60 . 6 5 8 0 E - 0 60 . 6 5 9 P E - 0 60 . 6 7 0 7 E - 0 60 . 6 5 2 0 E - 0 60 . 6 5 5 0 E - 0 60 . 6 6 5 0 E - 0 60 . 6 8 0 3 E - 0 60 . 6 3 6 6 E - 0 6

0 . 6 1 0 P E - 0 70 . 6 0 9 5 E - 0 70 . 6 2 5 3 E - 0 70 . 6 1 5 1 E - 0 70 . 6 1 4 1 E - 0 70 . 6 1 9 5 E - 0 70 . 6 0 7 6 E - 0 70 . 6 3 7 R E - 0 70 . 6 3 4 6 E - 0 70 . 6 7 7 3 E - 0 70 . 6 7 2 5 E - 0 70 . 7 1 1 9 E - 0 70 . 7 4 2 0 E - 0 70 . 7 3 5 3 E - 0 70 . 7 7 6 9 E - 0 7

hi

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TABLE 3-3 (C on t inue d) Gamma deca y r a t e s by 4 - p i io n iz a t i o n chamber

SAMPLE NUMBER

1919191919191919191919

1919191919191919191919191919191919191919191919191919

191919191919191919

AOA OAOAOAOAOAOAOAOAOAO

AOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOA OAOAOAOAOA OAOA OAOAO

AOAOAOAOAOAOAOAOAO

S I Z E( M I C R O N S )

2 8 3 0 W2 8 3 0 W2 8 3 0 W2 8 3 0 W2 8 3 0 W2 8 3 0 W2 8 3 0 W2 8 3 0 W2 8 3 0 W2 8 3 0 W2 8 3 0 W

1410W1410W141 OW1410W1410W1410W1410W1410W1410W1410W1410W1410W1410W1410W141 OW1410W1410W141 O W1410W1410W1410W141 O W1 OWI* OW14 OW1410W

71 OW7 1 OW71 OW71 O W71 OW7 1 0 W71 OW71 OW7 1 0 W

AGE C(DAYS)

3 8 . 9 9 3 04 1 . 9 7 5 04 5 . 9 5 5 04 8 * 9 2 5 05 6 * 1 0 3 06 2 . 0 3 2 07 6 . 1 2 8 08 4 . 0 2 6 0

1 0 6 . 0 2 1 01 5 0 . 9 8 1 02 2 7 . 1 5 0 0

3.18805.05805.97706.94007.88609.07309.1910

1 0 . 9 8 9 01 2 . 9 9 4 01 6 * 9 8 2 01 9 * 9 0 5 02 2 * 9 8 5 02 4 * 9 7 2 03 2 . 1 3 7 03 4 . 9 8 9 03 8 * 9 9 6 04 1 * 9 7 8 04 5 * 9 5 7 04 8 * 9 2 8 05 6 * 1 0 7 06 2 * 0 3 4 07 6 * 1 2 8 08 4 * 0 2 9 0

1 0 6 * 0 2 1 01 5 1 * 0 1 0 02 2 7 . 1 4 3 0

3.18805*05905*97806*94007*88609*07309*19102 0 * 9 8 9 012*9940

O R R E CT E D A C T I V I T Y(MA)

0 . 5 7 6 2 E - 0 R0 . 5 4 3 8 E - 0 80 . 5 0 5 6 E - 0 80 . 4900E-OP0.4430E-0R0 . 3 9 1 6 E - 0 80 . 3 3 0 2 E - 0 80 . 3 2 1 8 E - 0 80 . 2 5 0 7 E - O R0 , 1 8 2 4 E - 0 S0 . 9 6 1 2 E - 0 9

0 . 1 1 5 1 E - 0 60 . 5 2 3 2 E - 0 70 . 4 0 0 8 E - 0 70 . 3 2 6 8 E - 0 70 . 2 7 6 7 E - 0 70 . 2 3 2 4 E - 0 70 . 2 3 0 7 E - 0 70 , 1 9 3 1 E - 0 70 . 1 8 0 5 E - 0 70 . 1 3 2 9 E - 0 70 . 1 1 7 9 E - 0 70 . 1 0 5 3 E - 0 70 . 9 6 9 6 E - 0 80 . 8 0 1 2 E - 0 80 . 7 7 9 1 E - 0 80 . 7 1 4 2 E - 0 80 . 6 7 3 6 E - 0 80 . 6 2 9 0 E - 0 80 . 6 0 9 4 E - 0 80 . 5 4 3 3 F - 0 80 . 4 8 4 2 E - 0 80 . 3 9 6 6 E - 0 80 . 3 8 R 7 E - 0 80 . 3 2 6 0 E - 0 80 . 2 2 0 6 E - 0 80 , 1 2 5 4 E - 0 P

0 . 5 8 2 1 E - 0 70 , 2 6 5 B E - 0 70 . 2 0 5 5 E - 0 70 . 1 6 3 8 E - 0 70 . 1 3 0 4 E - 0 70 . 1 2 0 4 E - 0 70 , 1 1 5 3 E - 0 70 . 9 6 9 6 E - 0 80 . 8 0 2 4 E - 0 8

A C T I V I T Y A T

00000000000

00000000000000000Oi0OiOi0OiOi0(0

OiO IO IO IO I0|0|Oi0|

(MA)

I R026E-I 8 1 1 8 E-I 8 2 5 0 E-I 8 5 4 3E-891QE>i 8 7 5 8 E >I 8 8 0 2E-19391 E-I 9234E-I 96 5 2E- 7 8 2 9E-

.7146E-|71PRE- 7 33 5 E-

100 HR

-07-07-07-07 0 7-07-0707-07-07-07

-07-07-07

I 7 3 7 7 E - 0 7I 7 3 64E--07l 7 3 6 0 E - 0 7.7420E-( 7 7 1 3E-| 8 5 1 4E-8221E-( 8 5 4 3E-i 8 8 8 2 E-I 8 9 66E-

-07-07-07-0707-07-07

I 9 3 9 3 E - 0 7(9813E-(9949E"1006E"I1026E-(1063E-I1094E-

-0707-0 606-0606

i 1 0 8 3 E - 0 6i10 5 7 E -1134E-

.1200E-(1167E-1021E'

-0606060606

I 3 6 1 6 E - 0 7I 3 6 5 3E-3 7 6 1 E -

0 70 7

3 6 9 8 E - 0 73 4 7 1 E " 073 8 1 2 E - 0 73 7 1 0 E -3 8 7 3 E -3 7 8 4 E -

0 70 70 7

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TABLE 3 - 3 ( C o n t i n u e d ) Gamma d e c a y r a t e s b y 4 - p i i o n i z a t i o n ch a ir ib er

SAMPLE NUMBER

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO

19 AO19 AO19 AO


7 1 OW7 1 OW7 1 OW7 1 0 W7 1 OW7 1 0 W7 1 OW7 1 0 W7 1 OW7 1 OW7 1 OW7 1 OW7 1 OW7 1 0 W7 1 OW7 1 OW7 1 OW177W177W177W177W177WI 7 7 W177WI 7 7 W177W177W177Wr 7 7 W177W177W177W177W177W1 7 7 l177W177W177W1 7 7 W177W1 7 7 W177W1 7 7 W

124W124W124W

AGE( D A Y S )

1 6 * 9 8 5 01 9 * 9 0 7 02 2 * 9 8 7 02 4 * 9 7 2 03 2 * 1 3 8 03 4 . 9 8 9 03 8 . 9 9 9 04 1 . 9 8 0 04 5 . 9 6 0 04 8 . 9 3 2 05 6 . 1 0 8 06 2 . 0 3 6 07 6 . 1 2 9 08 4 . 0 3 0 0

1 0 6 . 0 2 1 01 5 1 . 0 1 0 02 2 7 . 1 4 6 0

3 . 1 8 8 05 . 0 6 0 05 . 9 7 9 06 . 9 4 1 07 . 8 8 6 09 * 0 7 6 09 * 1 9 1 01 0 * 9 8 9 01 2 * 9 9 4 0

1 6 * 9 8 7 01 9 * 9 0 9 02 2 * 9 8 9 02 4 . 9 7 6 C3 2 * 1 4 1 03 4 * 9 9 1 03 9 * 0 0 1 04 1 * 9 8 1 04 5 * 9 6 2 04 8 * 9 3 4 05 6 * 1 0 9 06 2 * 0 3 7 07 6 * 1 3 0 08 4 . 0 3 2 01 0 6 . 0 2 1 01 5 1 . 0 1 0 0

2 2 7 * 1 4 7 0

3 . 1 8 8 05 O S t O5 . 9 8 0 0

CORRE CT E D ACT IVIT Y(MA)

0 . 6 6 0 3 E - 0 80 . 5 8 5 1 E - 0 80 . 5 1 8 2 E - 0 80 . 4 8 0 6 E - 0R0 . 3 8 0 3 E - 0 80 . 3 5 8 7 E - 0 80 . 3 4 0 9 E - 0 80 . 3 3 2 8 E - 0 80 . 3 0 8 4 E - 0 80 . 2 9 6 5 E - 0 80 . 2 5 9 1 E - 0 80 . 2 5 2 6 E - 0 80 . 2 1 8 2 E - 0 R0 . 1 9 6 4 E - 0 80 . 1 5 8 3 E - 0 80 . 1 1 8 8 E - 0 R0 . 6 2 6 9 E - 0 9

0 . 5 6 9 6 E - 0 70 . 2 6 5 8 E - 0 70 . 2 0 7 2 E - 0 70 . 1 6 3 8 E - 0 70 . 1 3 S 7 E - 0 70 . 1 1 9 5 E - 0 70 . 1 1 3 7 E - 0 70 . 9 6 9 6 E - 0 80 . 8 0 2 4 E - 0 80 , 6 6 0 3 E - 0 80 . 5 6 0 0 E - 0 80 . 5 0 7 3 E - 0 80 . 4 5 9 7 E - 0 80 . 3 7 6 3 E - 0 B0 . 3 6 1 2 E - 0 80 . 3 3 2 8 E - 0 80 . 3 1 6 5 E - 0 80 . 2 9 6 2 E - 0 80 . 2 8 8 2 E - 0 80 , 2 5 9 1 E - 0 B0 . 2 1 8 9 E - 0 80 . 1 9 3 3 E - 0 80 . 1 7 9 7 E - 0 80 . 1 5 0 4 E - 0 80 . H 0 3 E - 0 80 . 5 8 S 1 E - 0 9

0 . 2 5 2 0 E - 0 70 . 1 2 1 2 E - 0 70 . 9 0 9 5 E - 0 8

A C T I V I T Y A T

00000000000000 |Oi00OiO IO I000Oi0000Oi0000000000OiO IO IO I

0 ,0 ,Oi

(MA)

i 4 0 8 5 E -| 4 2 4 2 E -I 4 3 7 1 E "I 4 4 4 4 E "( 4 4 5 9 E -. 4 5 1 8 E -

1 0 0 H R

- 0 7- 0 7- 0 7 0 7- 0 7- 0 7 4 7 4 9 E - 0 7( 4 9 6 8 E -( 5 0 3 2 E -I 5 1 6 9 E -I 5 2 1 8 E -

I 5 6 S 1 E - 5 8 1 7 E -I 5 7 3 2 E -> 5 8 4 8 E -( 6 2 8 6 E -I 5 1 0 6 E -

0 7- 0 7- 0 7- 0 7- 0 7- 0 7- 0 7- 0 7 0 7- 0 7

( 3 5 3 8 E - 0 7I 3 6 5 4 E - 0 7 3 7 9 3 E -i 3 6 9 9 E - 3 6 9 3 E -1 3 7 8 7 E -

0 7 0 7- 0 7 0 7I 3 6 5 6 E - 0 71 3 8 7 3 E - 3 7 8 4 E -( 4 0 8 6 E -( 4 0 6 0 E -i 4 2 8 0 E -

- 0 7- 0 7 0 7 0 7 0 7| 4 2 5 2 E ~ 0 7 4 4 1 2 E -( 4 5 4 9 E -I 4 6 3 6 E *I 4 7 2 6 E -i 4 8 3 4 E -I 5 0 2 6 E -| 5 2 1 8 E -

0 7 0 7- 0 7- 0 7 0 7 0 7 0 7

I 4 8 9 7 E - 0 7( 5 1 5 3 E - 0 7I 5 2 4 5 E - 0 7( 5 5 4 0 E -I 5 8 3 7 E -. 4 7 6 6 E *

0 7- 0 7 0 7

1 5 6 5 E - 0 71 6 6 7 E -1 6 6 6 E -

- 0 7 0 7

49

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TABLE 3 . 3 (Continued ) Gamma decay rat es b y 4 - p i ionization chamber

SAMPLE NUMBER

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO

19191919191919191919191919191919191919191919191919

AOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAO

SIZE(MICRONS)

124W124W124W124W124W124W124W124W124W124W124W124W124W124W124W124W124W124W124W124W124W124W124W

8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W8 8 W88Vt8 8 W

AGE(DAYS)

6*94107.88609*07609*194010*993012*994016*988019.911022.991024.976032*143034*992039*004041*984045*965048*937056*112062*038078J 131084.0330136*0210151.0100227.1500

3*18805*06305*98106*94407*88609*07609*194010*993012*997016*989019*912022*993024.976032.143034.993039.006041.987045.968048.9400

56.115062.039076.132084.0340106.0210151.0100

CORRECTED ACTIVI

0000000000000000Oio(OiOI0OI0

OiOiOiOiOIo1420E-08.1339E-08it217E-08il318E-08.1087E-08. I112E-08(9375E-091 1045E-08I6687E-09.3818E-092507E-09

I3147E-071513E-071213E-079278E-088024E-086770E-086770E-085600E-087313E-083594E-083093E-082758E-082466E-081861E-082070E-081704E-081664E-081501E-081565E-081337E-081053E-088960E-09P776E-097940E-094667E-09


*l23E-07.1691E-071722E-07.1721E-07I710E-071703E-071940E-07.1818E-07.1876E-07.1855E-07.2088E-071S40E-071979E-072000E-071987E-07.2298E-072188E-072486E-07.2499E-073049E-072462E-072021F-072042E-07

0.1955E-070.2082E-070.2221E-070.2096E-070.2136E-070.2145E-070.2178E-070.2238E-070.3450E-070.2224E-070.2243E-070.2327E-070.2280E-070.2183E-070.2607E-070.2375E-070.2485E-070.2450E-070.2729E-070.2693E-070.2354E-070.2389E-070.2561E-0702924E-070.2470E-07

50

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TABLE 3^3 (Continued) Gamma decay rates by k-pi ionization chamber

SAMPLE NUMBER

19 AO

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO

19 AO19 AO19 AO19 AO

SIZE(MICRONS)

88W

44W44W44W44W44W44W44W44W44 W44W44 W44W44W44W44W44W441*44W44W44W44W44W44W44W44 W44W

40W40W40W40W40W40W40W4 0 1 t f40W40W40W40W40W

30W30W30*30W

AGE(DAYS)

227*1500

3*18805*06405*98206.94507*88609.07609*197010.993012*997016.990019*913022*996024.976032*144034*995039*010041.991045.971048.942056*116062*039076.132084.0350106.0210151.0100227.1500

3*18005*05305*98306*94607.88909*07909*198011*006013*0000t*991019*9140e4.983032*1460

3*18005*05405I9S406*9490


0.2675E-09

0.9332E-070.4380E-070.3377E-070.2683E-070.2290E-070.1889E-070.1847E-070.1555E-070.1B38E-070.1011E-070.8442E-080.784 0E-080.7104E-080.5543E-0S0.5438E-080.4951E-080.4667E-080.4301E-080.4529E-080.3636E-080.3200E-080.2887E-080.2382E-080*2090E-080.1442E-080.8358E-09

0.2257E-080.9194E-090.8421E-090.6269E-090.5851E-090.5015E-090.5851E-090.5433E-090.4597E-090.3343E-090.58S1E-090.2507E-090.8092E-10

0.2215E-0S0.852SE-090.7158E-090.5433E-09


0.2179E-07

0.5796E-070.6030E-070.6187E-070.6062E-070.6096E-070.5986E-070.5946E-070.6214E-070.7254E-070.6259E-070.6122E-070.6615E-070.6571E-070.6500E-070.6850E-070.6899E-070.6970E-070.7021E-070.7900E-070.7323E-070.7158E-070.7697E-070.6952E-070.7695E-070.7633E-0706808E-07

O.I396E-080.1261E-080.1543E-080.1417E-080.1558E-080.1590E-090.1884E-080.2174E-080.2169E-0802069E-080.4243E-080.2320E-080.9490E-09

0,t370E-08O.U70E-080.1312E-080.1228E-08.

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TABLE 3.3 (Continued) Gamma decay rates by It-pi ionization chamber

SAMPLE NUMBER

19191919191919

AOAOAOAOAOAOAO19 AO

191919191919191919191919

1919191919191919191919


AOAOAOAOAOAOAOAOAOAOAO19 AO

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO'9 AO19 AO

SIZE(MICRONS)

30W30W30W30W30W30W30W30W

20W20W20W20W20W20W20W20W20W20W20W20W

10W10W10W10W10W10Wlow10W10Wlowlow10W

5W5W5W5W5W5W5W5W5W5W5W5W

A

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TABLE 3-3 (Continued) Gamma decay r a tes by i+-pi ioniz a tion chamber

SAMPLE NUMBER SIZE AGE CORRECTFD ACTIVITY ACTIVITY AT(MICRONS) (DAYS) (MA) (MA) 100 HR

19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO19 AO

3W3W3W3W3W3W3W3W3W3W3W3W

3.94805.05605.98906.95107.89209.08709.200011.006013.003016.997019.917032*1480

0.S262E-O90.3176E-090.235RE-090.1254E-090.1672E-090.1672E-090.2507E-090.2925E-090,2090E-090.1672F-090.4I79E-090,4046E-10

O.4730E-090.4360E-090.4328E-090.2836E-090.4454E-090,5305E-090.8074E-090,1171E-080.9861E-090.1035E-080.3031E-080.4745E-09

20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO20 AO

5.26005*97006*89507*87809*05609.188010*974012*966016*969019*889023*019024*975028*043032*125035*008038.965041.956045.936048.917056*120062*029076.140084.049091.0500105*9960150.9810227.0700

0.2966E-060.2361E-060. 1919E-060.1627E-060.1359E-060. 1292E-060.1083E-060.8743E-070.64B6E-070.550BE-070.4731E-070,43S5E-070.3715E-070.3326E-070.3878E-070.278RE-070.2506E-070.2323E.070.2149E-070.1886E-070.1735E-070.2250E-070, 1304E-070.1227E-070,1095E-070.7339E-080.4795E-08

0.4380E-060,4313E-060.4297E-060.4324E-060.4295E-060.4155E-060.4320E-0S0.4113E-060.A009E-060.3989E-060.3996E-060.4027E-060.3844E-060.3898E-060.4887E-060.3880E-060.3740E-060.3788E-060.3747E-060.3798E-060.3880E-060.5999E-060.3806E-060.3874E-060.4031E-060.3P83E-060.3Q03E-06

53

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TABLE 3.1* Mass and ac tiv ity di str ib ut io ns of d ebr is

SAMPLENUMBER SIZE(MICRONS)

28 3 01*71OW1T7W124Wsew44 W30 W20W10W5 W3W-1 W

283 OW14I0W71 OW177W124W8 8 W44 W30W20W10W5 W-!W

2830WJ410W710W177W124W8 8 W44 W30 W20Wlow-1W

MASS(GRAMS)

16,71000.10000.10001.77001.50001.33003.03000.14001.98003.24001.58000.72001.2200

17.64000.03000.13000.16002.53002.10001.93003.30000.32004.18001.14001.78000.0400

18.07000.12000.42001.77002.60000.74001.22003.24001.14001.52003.34001.9600

ACTIVITYAT 100 MR(MA>

0.5159E-060.4317E-080,1714E^080.2T27E-070.I761E-070,1991E-070.6387E-070.1126E-070.4090E-070.8881E-070.7S13E-070.2277E-070.14S4E-060.4670E-060.0,0,5593E-030.2580E-070.2529E-070.2905E-070.7165E-070.55S1E-070.6192E-070.5872E-070.2t*9E-080.1313E-06

0.5629E-060.1038E-090.2774E-070.6735E-070.1298E-060.1373E-070.1749E-070.5708E-070.2080E-070.2600E-070.7799E-070,1248E-06

C U M U L A T IV E D I S T R r B U T I O N S P E C I F I CP E R C EN T L E S S T H A N A C T I V I T YM A SS A C T I V I T Y ( M A / G R A M S )

999999999999910101010101010101010101010

131313131313131313131313

AOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAOAO


9 9 . 4 09 8 . 8 08 8 . 2 17 9 , 2 37 1 . 2 75 3 . 1 45 2 . 3 04 0 . 4 52 1 . 0 71 1 . 6 17 . 3 00 .

9 9 . 8 39 9 . 0 99 8 . 1 98 3 . 8 47 1 . 9 46 1 . 0 04 2 . 2 94 0 . 4 81 6 . 7 81 0 . 3 20 , 2 30 ,

9 9 . 3 49 7 . 0 18 7 . 2 27 2 , 8 36 8 . 7 36 1 . 9 84 4 . 0 53 7 . 7 42 9 , 3 31 0 , 8 50 .

9 9 . 1 69 8 . 8 39 4 , 7 19 1 , 2 98 7 , 4 47 5 . 0 67 2 . 8 76 4 . 9 54 7 . 7 33 3 . 1 72 8 . 7 60 .

1 0 0 , 0 01 0 0 , 0 09 8 . 8 09 3 . 2 88 7 . 8 68 1 . 6 46 6 . 3 05 4 . 4 14 1 . 1 62 8 . 5 82 8 . 1 20 .

9 9 . 9 89 5 . 0 58 3 . 0 96 0 . 0 35 7 . 5 95 4 . 4 84 4 . 3 44 0 . 6 53 6 . 0 32 2 . 1 70 .

0 . 4 3 1 7 E - 0 70 . 1 7 1 4 E - 0 70 . 1 2 0 2 E - 0 70 . I 1 7 4 E - 0 70 . I 4 9 7 E - 0 70 . 2 1 0 8 E - 0 70 . 8 0 3 9 E - 0 70 . 2 0 6 S E - 0 70 . 2 7 4 1 E - 0 70 . 4 7 5 5 E - 0 70 . 3 1 6 2 E - 0 70 . 1 2 1 6 E - 0 6

0 ,0 ,0 . 3 4 9 6 E - 0 70 . 1 0 2 0 E - 0 70 , 1 2 0 4 E - 0 70 . I 505E - O70 . 2 1 7 1 E - 0 70 . 1 7 3 S E - 0 60 . 1 4 8 1 E - 0 70 . 5 1 S 1 E - 0 70 . 1 2 0 7 E - 0 80 . 3 2 8 2 E - 0 5

0 . 8 6 5 2 E - 0 90 . 6 6 0 4 E - 0 70 . 3 8 0 5 E - 0 70 . 4 9 9 2 E - 0 70 . 1 8 5 6 E - 0 70 . 1 4 3 3 E - 0 70 . 1 7 6 2 E - 0 70 . 1 8 2 4 E - 0 70 . 1 7 1 0 E - 0 70 . Z 3 3 5 E - 0 70 . 6 3 6 7 E - 0 7

5h

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TABLE 3-1* (Cont inued) Mass and a c t i v i t y d i s t r i b u t i o n s of d e b r i s

SAMPLENUM8ER

19191919191919191919191919

2 02 0202 02 02 020202 02 02 0202020

1010101010101010

AOAOA OAOAOAOAOAOAOAOAOAOAO

AOAOAOAOA OAOAOAOAOAOAOAOAOAO

AOAOAOAOAOAOAOAO

1111111111111


2 8 3 014107 1 03 5 02 6 01 7 71241048 86 24 4

P AN

2 8 3 0 W1410W7 1 0 WI 7 7 W124W8 8 W4 4 W3 0W2 0 W10W5 W3W

- ! W

2 8 3 014107 1 01 7 78 84 4

P A N

M A S S(GRAMS)

1 1 7 . 5 9 0 02.97007.4800

10.03002.58002.01003,78008.58004.96007.1000

1 3 . 4 1 0 01 9 . 8 9 0 03 4 . 8 0 0 0

16.92000 .0 .0.02001.60002.15002.05004,28001.46002.26001,06000,64000,32001.0800

9 6 . 3 9 0 00.02000.06000.0700

13.06002 1 . 0 6 0 03 1 . 0 7 0 03 1 . 0 5 0 0

A C T I V I T YA T 100 HR

(MA)

0.3894E-050,1217E-060 ( 3 1 7 9 E - 0 60.2507E-060,JCS6E-060.6389E-070.5959E-060.1184E-060.7715E-070,12e9E-060.2761E-060.5995E-060.I235E-05

0.3320E-060 .0 .0.1049E-080.2905E-070.1877E-070.I815E-070.S590E-070.4173E-070.1031E-070.3134E-070.1670E-070.1565E-070.9332E-07

0.2785E-050.4597E-090.1572E-070.1870E-070.1262E-060.940IE-060.1368E-050,3158E-06

C U M U L A T I V EP E R C E N TM A S S

9 7 , 4 79 1 , 1 18 2 . 5 88 0 , 3 97 8 . 6 87 5 , 4 76 8 , 1 76 3 . 9 55 7 . 9 14 6 . 5 12 9 . 5 90 .

100.00100.009 9 . 8 89 0 . 4 37 7 . 7 26 5 , 6 040,313 1 , 6 81 8 , 3 21 2 , 0 68,276,380.

9 9 . 9 89 9 . 9 29 9 , 8 48 6 , 3 06 4 , 4 53 2 .210.

D I S T R I B U T I O NLES S THANA C T I V I T Y

9 6 . 8 88 8 . 7 18 2 . 2 87 9 . 4 97 7 . 8 56 2 . 5 45 9 . 5 05 7 . 5 25 4 , 2 14 7 , 1 23 1 , 7 30 ,

100,001 0 0 , 0 09 9 . 6 89 0 , 9 38 5 . 2 87 9 . 8 16 2 . 9 75 0 , 4 04 7 , 3 03 7 , 8 63 2 . 8 32 8 , 1 10 ,

9 9 , 9 89 9 , 4 29 8 . 7 59 4 . 2 26 0 , 4 71 1,340 .

S P E C I F I CA C T I V I T Y

( M A / G R A M S )

0.33E-070.4097E-070.4250E-070.2499E-070.4209E-070.3178E-070.1576E-060.1380E-070.1555E-070.1816E-070.2059E-070.3014E-070.3550E-07

0.0 .0.5244E-070.1816E-070.8732E-080.8851E-080.1306E-070.2858E-070.4560E-080.2957E-070.2610E-070.4891E-070.8641E-07

0.29E-070.2299E-070.2621E-060.2672E-060.9664E-080.4464E-070.4404E-070 , 1 0 1 7 E - 0 7

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TABLE 3.1* (Continued) Mass and activity distributions of debris

NUMBER

1212121212121212

1313131313131313

14141414141414142020202020202020

AOAOAOAOAOAOAOAO

AOAOAOAOAOAOAOAO

AOAOAOAOAOAOAOAO

AOAOAOAOAOAOAOAO

SIZE(MICRONS)

283014107 1017 78 844PAN

283014107 1017 78 844PAN

283014107 1017 78 844PAN

283014107 1017 78 844PAN

MASS(GRAMS)

199(02000,0.02000(05008(850035(020084(060071.0200

149.33000.82003.350010.500017.580017.080052(200047(8000

42(92000(08000.60005.25003.64006.40009.370017.5800

100.32000(02000(05000.250012.350023.750026.600037.3000

ACTIVITYAT 100 HR(MA)

0.2971E-050.0(6298E-100(1585E-080(1887E-060(5246E-060(9445E-060(1312E-05

0(4592E-050(5092E-070.1097E-06O.SltlE-060.9303E-060.2912E-060.1176E-050.1523E-05

0.I989E-050(6429E-09Od586E-070(t948E-060(1684E-060(2S27E-060.4082E-060.9484E-06

0.1898E-050.1725E-090.1725E-090.6292E-080.2231E-060.2347E-060.4083E-060.1025E-05

CUMULATIVEPERCENTMASS

100.0099(9999.9695.5277,9235.680.

99.4597.2190(1878(4066(9732(010(

99(8198(4286(1877(7062(7940(96o

99(9899(9399(6887(3763(7037.180.

DISTRIBUTIONLESS THANACTIVITY

100.00100.0099.9493.5975.9444.150.

98.8996(5085(3765(1258(7733(170(

99(9799(1789(3880(9168(2047(680.

99(9999.9899.6587.8975.5254.010.

SPECIFICACTIVITY(MA/GRAMS)

0.15E-070.0.3149E-080.3170E-070.2133E-070.1498E-070.1124E-070.1847E-07

0.31E-070.6210E-070.3275E-070.4867E-070.5292E-070.170SE-070.2252E-070.3187E-07

0.46E-070.8036E-080.2644E-070.371OE-070.4627E-070.3949E-070.4356E-070.5394E-07

0.19E-070.8626E-080(3451E-080(2517E-070.1806E-070.9884E-080.1535E-070.2748E-07

56

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TABLE 3-5 GASEOUS IODINE MEASURED PROM SHOT TIME UNTI LD+l

Debris in O.53 Mev Photons/secSamples at Zero Time in AglPrecipitate Measuredon 8 July at 2100 hrgrams

Covered sample 0.1 95Uncovered sample 95 -8 283

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TABLE 3.6 LOSS OP I ODINE FROM PARTICULATE DEBRIS BY AIR EXPOSURE

Sample

123k5678910

Durationof AirExposure

123k5678910

Reference 5 at 11

4-pi Activity at 11 DaysTotal

18 0 X18 5 x195 x17 0 X17 0 X165 x165 xl60 X160 X165 X

. days

ma10-910-910-910-910-910-910-910-910-910-9

Iodine

ma_-

15.6 X13.0 X13.2 X11.5 x10.5 X8.0 x6 .k x-l(ma)

10-9io-910-910-910-910-910-9

ObservedIodine/Total

0.08000.07&O.O776O.O697O.O6360.05000.0900

= 0.25Fission Product (ma)

ObservedI x 100Expected I*

33-330.531.127.925.if20.016.0

expected

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TABLE 3-7 THREE DAY LEACHING

Sample

pH 1.042 mesh150 "325 "Pan "

pH 4.042 mesh150 "325 "Pan "pH 6.042 mesh150 "325 "Pan "pH 10.0k 2 mesh150 "325 "Pan "

Measured onTota l Samplema x 10

7 , 3606,0108,04815,19027 , 1205,5628,42016 , 82024 , 064

5,5097 , 6o415 , 8008,0404 , 6 4 07,17014 , 950

9 JuiLy 196225 m l S o lu t i onma x 10

3404406782,42039 05021,0602 , 8603025479422 , 5 4 223 0350730990

$ Leached

4 . 6 17 - 328 . 4215-931.449-021 2 . 5 81 7 . 01.259-931 2 . 3 91 6 . 32 . 8 67-541 0 . 26 . 62

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TABLE 3 . 8 EIGHT DAY LEACHINGSample Measured on 14 Ju ly 1962 LeachedT ot a l Sample 25 ml So lu t io n

pH 1.042 mesh150 mesh325 meshPan meshpH 4.042 mesh150 mesh325 meshPan meshpH 6.042 mesh

150 mesh325 meshPan meshpH 10.042 mesh150 mesh325 meshPan mesh

, ~ 1 1ma x 10

41951855133536702805133018203625

41301320186536601920153018953630

- ^ Hma x 10

13 519 5125410

45701103657060125350

4o7013 5350

3 . 2 21 0 . 5 19 . 3 61 1 . 21.605 . 2 66.041 0 . 0 7

1.644 . 5 46 .709 . 5 62 . 0 84 . 5 87 . 1 29 .64

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TABLE 3.9 THREE DAY EXCHANGE

Measured on 9 July 1962 $ ExchangeTotal Sample Adobema x 10 1 ma x 10 1

Adobe Total Adobe42 mesh150 mesh325 meshClay42 mesh150 mesh325 mesh

457033805900Total5O0033005&00

2154303050Clay30095 0

4120

4.7012.7251.69

5.1728.7971.03

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TABLE 3.10 NRDL SEDAN RADIOCHEMICAL RESULTSUnits: Equivalent Fissions/Gm

Station Screen IsotopeNo. Retained On Value StandardDeviationTyler Mesh

10 7, 12, 24

10

10

10

10

80

170

325

Pan

12 7 ; 12, 24

Sr ,Sr ;Z r

89.9091.95

Z r 9 5Sr-89s >v 9 i,95

.89,90Z rSr,Sr;.91Z rSr ,SZ r

.958919091.9589,9091

Sr(Sr ;Y^Z r 9 5

2 . 2 5 x 1 0 ^4 . 1 5 x 1 0 ^6.52x10773.89xioxl1.29x101.35x102 . 31x103 . 19x10

10121 11 15.26X10H"8 . 8 8 x l o | |6 . 7 2 x i o r |7 . 00x101.05x10:1.64x109.21x10:5 .49x10

121211112.27x10^4.25xio|r3.70xlo:H-4.99x104.51x10

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TABLE 3.10 (CONTINUED) NRDL SEDAN RADIOCHEMICAL RESULTSUnits: Equivalent Fissions/Gm

StationNo.

ScreenRetained On Isotope ValueStandardDeviation

12Tyler Mesh

80

12

12

12

17 0

325

Pan

1Z r 9 5M o "R n 1 0 3>6> 3 1T e 1 3 1T e 1 3 2C s 1 3 6C s 1 3 7; s l 4 0? H n? 1 4 4>S r 8 9Sr;90

Y 9 1Z r 9 5

Sr;89,9091

Z r 9 5S r 89

S r 90

1.90x10?-?-3 - 3 2 x 1 0 ^7 . 2 7 x 1 0 ^4 . 9 5 x 1 0 ^5-06x103 . 9 7 X 1 0 1 12 . 0 8 x 1 0 ^< 4 . 8 8 x 1 0 ^2.02x10^74 .2 4 x l 0 7 p1 . 5 0 X K C1 . 3 7 x 1 0 ^1 . 4 4 x l 0 1 24 .2 3 x 1 05.60x10:4 .00x105.7OXIO

11111111121.15x10^

1.64x10^115.68x105.16x10

6 . 3 4 x 1 0 ^1 . 9 2 x l 0 | ;1 .08x10^ ,5-17x10771 . 9 3 x 1 0 ^1 .48x10"^

3-7+ 3-0+ 2.3

1 5 .5+ 7 . 2+ 1 1 .0

+ 3.4

+ 5.0U ni ts = Atoms

( C o n t i n u e d )63

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TABLE 3-10 (CONTINUED) NRDL SEDAN RADIOCHEMICAL RESULTSUnits: Equivalent Fissions/Gm

Station Screen IsotopeNo. Retained On

Value StandardDeviation

12

12

Tyler MeshPan

Pan

,91

Sr95

Mo 9

Ru 03

6.20xloH-7-77x10779.20x10777.29x102.81x101.94x101.55x102.43x103.84x10

11il1111 2.9

12

12

Pan

Pan

106Ru

jl31

Te'131

5-55x1011

5.85x1011 + 4.1

12 Pan

Te132

Cs136

Cs137

4.51x10117-42x1010

1.50x10115.25x105-99x109-99x10

111111

+ 7-3

+ 2.2

(Continued)64

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Station Screen IsotopeNo. Retained On Value StandardDeviationT12

12

Tyler MeshPan

Pan

13

13 12

13 24

13 80

Units = Atoms

Ba'40

Ce 41

Ce 44

*&

115.78x107.75xloH-9.06xl0xx2.96x102.43x10

1111

2.32x10 1

Y91Z r 9 5S r 8 9S r 9 0y91Z r 9 5

Y 9 lZ r 9 5S r 8 9S r 9 0Z r 9 5

2.19x10 *6.29x10?-?-9.85x10?-;2.07x107^4.47x101.85x10^3 . 4 8 x 1 0 ^5.88x10?"?-4.32xl0X J-4.45x10?"?-6.23x10?-?-8.81x107?;4.99x104.19x10?-?-6.37xl0?-xl .39xlO x f1.94x10 x

+ 14.3

+ 2.7

+ 12.0

(Continued)65

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Station Screen IsotopeNo. Retained On Value S t a n d a r dD e v i a t i o nTyler Mesh

13 170

13

13

32 5

Pan

14 7, 12

14 24

Sr,Sr ;.99,9091

Zr 9 5.89.90r(>

Zr 9 5q 89s>Zr9 5Sr ,Sr;

89,9091Z?^

$y9 1^ 9> 3 1T e 1 3 1T e 1 3 2C s 1 3 6C s 1 3 7Sl40^ 1 4 1? iS> 5

5.05x10?-?-4.83x10773-93x10?-?-4 . 8 7 X 1 0 1 11.22x109.66x106.22x10

121 11 14 6 X 1 0 1 1

2 .60x107^2.32x107"-7.82x107?-3.16x102.60x105-7-1 .

2 i x i o :47x1011x10

1 11 11 112

2.11x104.02x101.53x101.06x101.17x102.13x104.88x10

1 11 11212121 11 1

3 - 5 1 x 1 0 ^1.07x107''2 .5 7 x l 0 ? " |7 . 5 9 x 1 0 ^< 8.63x10^1.24x107^3-28xlO X *

1 3 .3+ 4 .0

7 .38.39 .57 . 13.74 . 3

+ 4 .6* U ni ts = Atoms( C o n t i n u e d )

6 6

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TABLE 3.10 (CONTINUED) NRDL SEDAN RADIOCHEMICAL RESULTSUnits: Equivalent Fission/Gm

StationNo.

ScreenRetained On

Isotope Value StandardDeviation

14Tyler Mesh

8 0

14

14

Ik

170

325

Pan

Sr 8?* $ Zr 9 5S>i5*106^ 1 3 1T e 1 3 1T e 1 3 2C s 1 3 6C s 1 3 7; s i 4 o? 1 4 4> 5Sr,Sr;Z r

.89.9091,95S r 8 9S r 9 0y9 1Z r 9 5Sr ,Sr ;

.89.909 1Zr;Mo:Ru 'Ru:

.95,991031061 3 1

2.61x10?-?-4 .66x10?- ;1.78x10;;1.24x107^1.27x10

1.70X10113.91x10?"

pne 229 Sedan

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