Nuclear Data for Transmutation: status, needs and methods Review of the available experimental and...

Nuclear Data for Transmutation status needs and methods

Review of the available experimental and evaluated capture cross section data

for 241Am and 243Am

Nikola VasilevInstitute for Nuclear Researches and Nuclear EnergyBulgarian Academy of Sciences

Second IP EUROTRANS Internal Training Course Nuclear Data for Transmutation status needs and methods Santiago de Compostela (Spain) June 7 - 10 2006


Objectives

Introduction

bullNuclear Waste

bullMinor actinides

bullAmericium

bullRadiotoxicity amp Solutions

bullCross section data

bullAvailable Evaluated Data Files for Americium

bullAvailable Experimental Data for Americium


Spent Nuclear Fuel Waste

bull Elements with more than 92 protons Transuranium elements (TRU)

bull Fission products

bull Neptunium americium amp curium Minor Actinides (MA)


Nuclear power plants generate long lived radiotoxic nuclides through the reactions

n + 235U rarr fission products + + + e- + n

The fission reaction is however not the only reaction that can result from neutron

absorption in uranium The capture reaction denoted as (n) leads to the

Transuranium or Actinides production

n + 238U rarr 239U + rarr 239Np + n + e- rarr 239Pu + n + e- rarrhelliphellip etc

n + 239Pu rarr 240Pu +

n + 240Pu rarr 241Pu + rarr 241Am + + e-


Americium appears in the nuclear system in two ways

beta decay of 241Pu241Pu 1048823 rarr 241Am +

neutron capture on 242Pu

n + 242Pu 1048823 rarr 243Pu rarr 1048823 243Am +

241Am

243Am

T12

T12

1425plusmn100 b

587plusmn12 b

Thermal Capture

Thermal Capture

Data taken from Mughabghab

751plusmn18 b1820plusmn70 b

4322 y

7370 y


The radiotoxicity values are relative to the radiotoxicity (horizontal line) of the quantity of uranium ore that was originally mined to produce the fuel (eight tons of natural uranium yields one ton of enriched uranium 35 235U)

Radiotoxicity in spent nuclear fuel


Possible Solutions

Repository How long is it possible to be stored

Isnrsquot it Very hazardous

Transmutation

in existing facilities like HWR amp LWR

or

Accelerator Driven Systemsand Fast Reactors

Probably the more sophisticated and clever way is


Accurate and reliable neutron capture cross section data for MA are necessary for the proper design safety regulation and precise performance

assessment of transmutation

At the present moment evaluated cross section files for 241Am exist in all recent releases of the available evaluated cross section libraries ENDF

JEFF JENDL BROND and CENDL

Cross section status and needs

At the very beginning detailed knowledge of the available DATA SETS is very important


Americium 241 Capture Cross Sections Data

bullThermal Energy Range1 vUp to 015 eV

bullResolved Resonances190 number of resonances are observedRR Range015 eV to 150eV

bullUnresolved ResonanceRR Range150eV up to 4000eV


lib RRRE - range

formula authors year restot s neg

EXFORData used

ENDFB-VI 1E-5 15E2 eV SLBW Young Madland Zhou et al

195 190 5 Darrien Vanpraet Wisshak

JEF 30 1E-5 15E2 eV SLBW Conde et al 190 189 1

JENDL 33 1E-5 15E2 eV MLBW TNakagavaOIwamoto

2001

195 190 5 Adamchuk Derrien and Lucas9543 1451 182

Bowman Gerasimov Dabbs9543 1451 183

Weston and Todd Vanpraet

CENDL 21 1E-5 15E2 eV Zhou Delin Gu Fuhua et al

195 190 5

BROND 2 1E-5 15E2 eV MLBW AIBlokhinVMMaslov

Oct90

190 189 1 CaptureVanpraet(VA76)TransPhillips(PH79)

Recent releases of evaluated files libraries


lib LAB EVALUATORS DATE

ENDFB-VI LANL CNDC Young Madland Zhou et al August 1994

JEF 30 NEA H Conde June 1982

JENDL 33 JAERI Nakagava Iwamoto et al March 2001

CENDL 21 CNDC Zhou Delin Gu Fuhua et al June 1992

BROND 2 FEI IJE Blokhin Maslov et al December 1990

ENDF B-VI8

Resolved resonance parameters in the energy range 10E-5 eV to 150 eV are derrived by means of SLBW formula and five negative resonances were added

JEF 30

Resolved resonance parameters in 10E-5 eV to 150 eV The RRP were adopted by means of SLBW formula and one negative resonance was added

JENDL 33

Resolved resonance parameters in the energy range 10E-5 eV to 150 eV are derrived by means of MLBW formula and five negative resonances were added The resonance parameters were adopted by Maslov which were mainly taken from Darrien et al transmission measurements

BROND 2

Resolved resonance parameters in 10E-5 eV to 150 eV data were taken from JENDL 30 with small corrections The RRP were adopted by means of MLBW formula and one negative resonance was added

Evaluated Data Files for 241Am


Most recent releases of evaluated (nγ) cross sectionin thermal and resonance energy region


Comparison between ENDFB-VI8 and BROND 22 MT=102

energy region 20eV - 40eV

6 times higher


Shape and amplitude difference as well as energy shifting between the evaluated files for MT=102


BROND vs ENDFB-VI8 in energy range 140eV-150ev MT=102


Unresolved Resonance Region

Due to the lack of experimental data in the unresolved resonance region the discrepancy of the evaluated data from the different libraries become

more visible since it is 5 up to

20keV and 10 or larger above


Resolved amp Unresolved resonance region


Significant differences are found in the resolved resonance region

bullup to 30eV mainly in the shape of the resonances

bullThe evaluated file from BROND contains few strong resonances that are not included into the other libraries

RRR

URR

bullthe discrepancy of the evaluated data from the different libraries become more visible in Unresolved Resonance Region since it is 5 up to 20keV and 10 or larger above


Am-241 RRR Average Parameters

lib t n f

ENDF B-VI8 004684 000124 004530 000030

JEFF 30 004018 000055 003943 000021

JENDL 33 005012 000120 004858 000034

BROND 2 004849 000136 004691 000023

CENDL 21 004684 000124 004530 000030

1 2 3 4 5 6

00

02

p(x

)

x = n lt n gt

Porter Thomas distribution

ENDFB - VI8

Neutron Width distribution

1 2 3 4 5000

005

010

015

P(x

)

x = D lt D gt

Wigner distribution

ENDF B - VI

Level spacing distribution

lt D gt = 078747 eV

Available Experimental Data Sets


bull Few different ToF capture data sets are available in the resolved resonance region the (nabs) data from Weston et al and Todd et al the (nγ) data from Vanpraet et al and the (nγ) measurements of Gayther et al

bull In the unresolved resonance region the above mentioned data as well as the data of Wisshak amp Kaeppeler are available

bull No experimental data above 400keV are available except few activation measurements as well as 9 data points (nγ) measurement of Florov in energy range from 3e5 eV to 680e5 eV


bullThe uncertainties in these measurements vary between 05 and 10 (gt10 Gayther data set)

bull Into the lower energies of resolved resonance region (first few resonances) a large difference between Vanpraet data and other data sets

was found as the difference is up to 30

bullThis difference should be due to the not correct self shielding effects account or not enough correct application of weighting technique

bullAdditional resonance parameters can be found in Weston measurements and in transmissionfission measurements of Derrien at el


Energy Range

eV

Experimental Technique

Facility Detector Min and Max Uncertainties

Experimental Data

of Ref Remarks

104E4-23E5

Maxon RaePlus ngamma discrimination

Van de Graaff ToF FZK Karlsruhe

Maxon Rae plus Liq

Scintillator

5-10 CSR22 Wisshak amp Kaeppeler

1980

CrossSection Sum241Am(ng)

79Au(ng)WorkSubwork 20774-002

686E-1 ndash 15E5

Total Energy Detector(Mayer-

Leibniz weighting)

LINAC GELINA ToF

C6D6

Liq Scintillator

05 - 10 CS 7356 Vanpraet et al

1985

CrossSection

WorkSubwork 21978-003

128- 149 E2

Transmission and Fission

LINACSaclay ToF

10B-NaI plus LiqScintillato

r Ne226 for neutrons

2 - 5 RP78 Derrien et al

1975

Res WidthsWork

Subwor20415-005

10E-2- 5E5

Total Energy Detector

LINACHarwellToF

Liq Scintillator

tank

gt10 CS39 Gayther1977

CrossSectionWorkSubwork 20415-005

-22E- 494E


LINACORELA ToF

Liq Scintillator

NE226

7-5 RP7 Weston1976

Res WidthWorkSubwork 10767-003

Neutron Capture EXFOR Data Set for 241Am

Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002

Neutron Absorption EXFOR Data Set for 241Am

Neutron Total Cross Section EXFOR Data Set for 241Am

Energy Range eV


Facility Detector Min and Max

Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF

10B-NaI plus LiqScintillator

Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF

Scintillator CS32 TWPhillips1979

WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF

He-3 proportional counters

CS2985 TSBelanova1976

WorkSubwork4

0305004



Vanpraet et al

bull Capture cross section bull 241Am in a metallic form bullToF on LINAC GELINA bull C6D6 detector (weighted by Meyer- Leibniz )bull Neutron flux has been measured through 10B (nαγ) 7Li reaction by two C6D6 detectors bull Energy range 686E-1 eV ndash 15E5 eV

bullThe total uncertainties of cross section have been estimated up to 7


Weston amp Todd

bullAbsorption cross section bullSample in form of AmO2 bullToF on LINAC ORELA in Oak RidgebullLiquid scintillators NE226 (weighted by Macklin amp

Gibbons approach )bullNeutron flux from thermal energies to 2keV has been

monitored by a 10BF3 ionization chamber bullEnergy range from 001eV to 20keV

bullThe total uncertainties are between 5 and 7

Wisshak amp Kappeler

bullCapture cross sectionbullSamples from AmO2

bullToF on 3 MV Van de Graaff in Forzshungtzentrum Karlsruhe bullMaxon Rae detector and liquid scintillator

bullDetailed description of the uncertainties that are in 5 and 10 range


ToF capture data sets available in the Resolved Resonance Region


ToF capture data sets available in the Unresolved Resonance Region

bullThere are discrepancies in the evaluated files from different libraries

bullFor a conceptual design and safety operation of transmutation devices it is required to be clarified the origin and reasons for them

bullThe accuracy of evaluated data files should corresponds to the design requirements

bullNew top accuracy measurements and sophisticated analysis of 241Am resonance data are needed


Resume of 241Am capture cross section data sets



bullResolved Resonances220 number of resonances are observedRR Range020 eV to 250eV( 020eV to 210ev in BROND 2 )


Americium-243 Capture Cross Sections Data




ENDFB-VI LANL CNDC PG Young LW

Weston et al

September 96


JENDL 33 MINSK JAERI VM Maslov T

Nakagawa et al

January 2002

CENDL 21 none none none

BROND 2 FEI IJE Blokhin Maslov et al October 90

bull The ENDF JENDL JEFF and BROND libraries do contain evaluated files for 243Am bull No evaluated file exists from the CENDL cross section library

bull The discrepancies between libraries in the unresolved resonance region and resolved resonance region are significant

JENDL 33 contain the latest evaluated file for 243Am


Most recent releases of evaluated (nγ) cross sectionFor Am-243 in thermal and resonance energy region


JENDL 33 vs ENDFB-VI8 in energy range 90 eV-110eV MT=102


JENDL 33 vs ENDFB-VI8 in energy range 190 eV - 220eV MT=102


JENDL 33 vs ENDFB-VI8 in energy range 130 eV ndash 255 eV MT=102


BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s

Porter - Thomasdistribution

JENDL 33 gammawidths distribution

= 43067meV

243Am distribution of capture widths

00 05 10 15 20 25 30 35 40000

006

012

018

243Am level spacing distribution

p(x

)

x = D lt D gt

Wigner distribution JENDL 33 level

spacing distribution

lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n

Porter Thomasdistribution

JENDL 33 Neutron widths distribution

n gt = 01854meV

243Am neutron widths distribution

Preliminary analysis ofResonance parameters of 243Am (data taken from JENDL 33)

Energy Range eV



Uncert

Experimental Data

of Ref Rem

57e3 -921e4 Maxon RaePlus ngamma discrimination

NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1

Transmission LINACORELA

ToF

6Li glass scintillator

10 RP23 Simpson et al1974

WorkSubwork204

15003

05eV-1000eV Transmission LINACORELA

ToF


Not given CS5945Thin sample2793 batom

Simpson et al1974

WorkSubwork102

04004


ToF


Not given CS2337Thick sample12882 batom

Simpson et al1974

WorkSubwork102

04004


Available Experimental Data Sets for Am-243


The amount of available data for 243Am(nγ) is scarce In the resolved resonance region experimental radiative widths have been obtained indirectly from transmission measurements of Simpson et aland few fission ToF measurements

No direct ToF capture cross section data have been found

In the unresolved resonance region up to 1 MeV there exist only two TOF data sets by Wisshak et al and Weston et al ranging from 03 keV to 100 keV and 5 keV to 100 keV respectively

No data are available above 100 keV


bull Energy Shifting between JENDL 33 and other libraries

bull Large Shape Differences

bull Discrepancies in Resonance Parameters between Libraries

bull Lack of Experimental Data



New top accuracy measurements and sophisticated analysis of 243Am resonance

data

ARE HIGHLY NEEDED



Thank you for attention

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Objectives

Introduction

bullNuclear Waste

bullMinor actinides

bullAmericium

bullRadiotoxicity amp Solutions

bullCross section data

bullAvailable Evaluated Data Files for Americium

bullAvailable Experimental Data for Americium




















241Am

243Am

T12

T12

1425plusmn100 b

587plusmn12 b

Thermal Capture

Thermal Capture



4322 y

7370 y





Possible Solutions



Transmutation


or
















lib RRRE - range


EXFORData used





2001





195 190 5


Oct90










ENDF B-VI8


JEF 30


JENDL 33


BROND 2








6 times higher
















RRR

URR




lib t n f

ENDF B-VI8 004684 000124 004530 000030

JEFF 30 004018 000055 003943 000021

JENDL 33 005012 000120 004858 000034

BROND 2 004849 000136 004691 000023

CENDL 21 004684 000124 004530 000030

1 2 3 4 5 6

00

02

p(x

)

x = n lt n gt


ENDFB - VI8


1 2 3 4 5000

005

010

015

P(x

)

x = D lt D gt

Wigner distribution

ENDF B - VI


lt D gt = 078747 eV













Energy Range

eV



Experimental Data

of Ref Remarks

104E4-23E5



Maxon Rae plus Liq

Scintillator


1980



686E-1 ndash 15E5


Leibniz weighting)

LINAC GELINA ToF

C6D6

Liq Scintillator


1985

CrossSection


128- 149 E2


LINACSaclay ToF




1975

Res WidthsWork

Subwor20415-005

10E-2- 5E5


LINACHarwellToF

Liq Scintillator

tank



-22E- 494E


LINACORELA ToF

Liq Scintillator

NE226

7-5 RP7 Weston1976



Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002



Energy Range eV



Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF


Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF


WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF



WorkSubwork4

0305004



Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




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241Am

243Am

T12

T12

1425plusmn100 b

587plusmn12 b

Thermal Capture

Thermal Capture



4322 y

7370 y





Possible Solutions



Transmutation


or
















lib RRRE - range


EXFORData used





2001





195 190 5


Oct90










ENDF B-VI8


JEF 30


JENDL 33


BROND 2








6 times higher
















RRR

URR




lib t n f

ENDF B-VI8 004684 000124 004530 000030

JEFF 30 004018 000055 003943 000021

JENDL 33 005012 000120 004858 000034

BROND 2 004849 000136 004691 000023

CENDL 21 004684 000124 004530 000030

1 2 3 4 5 6

00

02

p(x

)

x = n lt n gt


ENDFB - VI8


1 2 3 4 5000

005

010

015

P(x

)

x = D lt D gt

Wigner distribution

ENDF B - VI


lt D gt = 078747 eV













Energy Range

eV



Experimental Data

of Ref Remarks

104E4-23E5



Maxon Rae plus Liq

Scintillator


1980



686E-1 ndash 15E5


Leibniz weighting)

LINAC GELINA ToF

C6D6

Liq Scintillator


1985

CrossSection


128- 149 E2


LINACSaclay ToF




1975

Res WidthsWork

Subwor20415-005

10E-2- 5E5


LINACHarwellToF

Liq Scintillator

tank



-22E- 494E


LINACORELA ToF

Liq Scintillator

NE226

7-5 RP7 Weston1976



Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002



Energy Range eV



Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF


Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF


WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF



WorkSubwork4

0305004



Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




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Possible Solutions



Transmutation


or
















lib RRRE - range


EXFORData used





2001





195 190 5


Oct90










ENDF B-VI8


JEF 30


JENDL 33


BROND 2








6 times higher
















RRR

URR




lib t n f

ENDF B-VI8 004684 000124 004530 000030

JEFF 30 004018 000055 003943 000021

JENDL 33 005012 000120 004858 000034

BROND 2 004849 000136 004691 000023

CENDL 21 004684 000124 004530 000030

1 2 3 4 5 6

00

02

p(x

)

x = n lt n gt


ENDFB - VI8


1 2 3 4 5000

005

010

015

P(x

)

x = D lt D gt

Wigner distribution

ENDF B - VI


lt D gt = 078747 eV













Energy Range

eV



Experimental Data

of Ref Remarks

104E4-23E5



Maxon Rae plus Liq

Scintillator


1980



686E-1 ndash 15E5


Leibniz weighting)

LINAC GELINA ToF

C6D6

Liq Scintillator


1985

CrossSection


128- 149 E2


LINACSaclay ToF




1975

Res WidthsWork

Subwor20415-005

10E-2- 5E5


LINACHarwellToF

Liq Scintillator

tank



-22E- 494E


LINACORELA ToF

Liq Scintillator

NE226

7-5 RP7 Weston1976



Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002



Energy Range eV



Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF


Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF


WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF



WorkSubwork4

0305004



Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




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Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

Slide 14

Slide 15

Slide 16

Slide 17

Slide 18

Slide 19

Slide 20

Slide 21

Slide 22

Slide 23

Slide 24

Slide 25

Slide 26

Slide 27

Slide 28

Slide 29

Slide 30

Slide 31

Slide 32

Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43














lib RRRE - range


EXFORData used





2001





195 190 5


Oct90










ENDF B-VI8


JEF 30


JENDL 33


BROND 2








6 times higher
















RRR

URR




lib t n f

ENDF B-VI8 004684 000124 004530 000030

JEFF 30 004018 000055 003943 000021

JENDL 33 005012 000120 004858 000034

BROND 2 004849 000136 004691 000023

CENDL 21 004684 000124 004530 000030

1 2 3 4 5 6

00

02

p(x

)

x = n lt n gt


ENDFB - VI8


1 2 3 4 5000

005

010

015

P(x

)

x = D lt D gt

Wigner distribution

ENDF B - VI


lt D gt = 078747 eV













Energy Range

eV



Experimental Data

of Ref Remarks

104E4-23E5



Maxon Rae plus Liq

Scintillator


1980



686E-1 ndash 15E5


Leibniz weighting)

LINAC GELINA ToF

C6D6

Liq Scintillator


1985

CrossSection


128- 149 E2


LINACSaclay ToF




1975

Res WidthsWork

Subwor20415-005

10E-2- 5E5


LINACHarwellToF

Liq Scintillator

tank



-22E- 494E


LINACORELA ToF

Liq Scintillator

NE226

7-5 RP7 Weston1976



Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002



Energy Range eV



Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF


Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF


WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF



WorkSubwork4

0305004



Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

Slide 14

Slide 15

Slide 16

Slide 17

Slide 18

Slide 19

Slide 20

Slide 21

Slide 22

Slide 23

Slide 24

Slide 25

Slide 26

Slide 27

Slide 28

Slide 29

Slide 30

Slide 31

Slide 32

Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43








ENDF B-VI8


JEF 30


JENDL 33


BROND 2








6 times higher
















RRR

URR




lib t n f

ENDF B-VI8 004684 000124 004530 000030

JEFF 30 004018 000055 003943 000021

JENDL 33 005012 000120 004858 000034

BROND 2 004849 000136 004691 000023

CENDL 21 004684 000124 004530 000030

1 2 3 4 5 6

00

02

p(x

)

x = n lt n gt


ENDFB - VI8


1 2 3 4 5000

005

010

015

P(x

)

x = D lt D gt

Wigner distribution

ENDF B - VI


lt D gt = 078747 eV













Energy Range

eV



Experimental Data

of Ref Remarks

104E4-23E5



Maxon Rae plus Liq

Scintillator


1980



686E-1 ndash 15E5


Leibniz weighting)

LINAC GELINA ToF

C6D6

Liq Scintillator


1985

CrossSection


128- 149 E2


LINACSaclay ToF




1975

Res WidthsWork

Subwor20415-005

10E-2- 5E5


LINACHarwellToF

Liq Scintillator

tank



-22E- 494E


LINACORELA ToF

Liq Scintillator

NE226

7-5 RP7 Weston1976



Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002



Energy Range eV



Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF


Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF


WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF



WorkSubwork4

0305004



Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

Slide 14

Slide 15

Slide 16

Slide 17

Slide 18

Slide 19

Slide 20

Slide 21

Slide 22

Slide 23

Slide 24

Slide 25

Slide 26

Slide 27

Slide 28

Slide 29

Slide 30

Slide 31

Slide 32

Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43






6 times higher
















RRR

URR




lib t n f

ENDF B-VI8 004684 000124 004530 000030

JEFF 30 004018 000055 003943 000021

JENDL 33 005012 000120 004858 000034

BROND 2 004849 000136 004691 000023

CENDL 21 004684 000124 004530 000030

1 2 3 4 5 6

00

02

p(x

)

x = n lt n gt


ENDFB - VI8


1 2 3 4 5000

005

010

015

P(x

)

x = D lt D gt

Wigner distribution

ENDF B - VI


lt D gt = 078747 eV













Energy Range

eV



Experimental Data

of Ref Remarks

104E4-23E5



Maxon Rae plus Liq

Scintillator


1980



686E-1 ndash 15E5


Leibniz weighting)

LINAC GELINA ToF

C6D6

Liq Scintillator


1985

CrossSection


128- 149 E2


LINACSaclay ToF




1975

Res WidthsWork

Subwor20415-005

10E-2- 5E5


LINACHarwellToF

Liq Scintillator

tank



-22E- 494E


LINACORELA ToF

Liq Scintillator

NE226

7-5 RP7 Weston1976



Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002



Energy Range eV



Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF


Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF


WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF



WorkSubwork4

0305004



Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

Slide 14

Slide 15

Slide 16

Slide 17

Slide 18

Slide 19

Slide 20

Slide 21

Slide 22

Slide 23

Slide 24

Slide 25

Slide 26

Slide 27

Slide 28

Slide 29

Slide 30

Slide 31

Slide 32

Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43
















RRR

URR




lib t n f

ENDF B-VI8 004684 000124 004530 000030

JEFF 30 004018 000055 003943 000021

JENDL 33 005012 000120 004858 000034

BROND 2 004849 000136 004691 000023

CENDL 21 004684 000124 004530 000030

1 2 3 4 5 6

00

02

p(x

)

x = n lt n gt


ENDFB - VI8


1 2 3 4 5000

005

010

015

P(x

)

x = D lt D gt

Wigner distribution

ENDF B - VI


lt D gt = 078747 eV













Energy Range

eV



Experimental Data

of Ref Remarks

104E4-23E5



Maxon Rae plus Liq

Scintillator


1980



686E-1 ndash 15E5


Leibniz weighting)

LINAC GELINA ToF

C6D6

Liq Scintillator


1985

CrossSection


128- 149 E2


LINACSaclay ToF




1975

Res WidthsWork

Subwor20415-005

10E-2- 5E5


LINACHarwellToF

Liq Scintillator

tank



-22E- 494E


LINACORELA ToF

Liq Scintillator

NE226

7-5 RP7 Weston1976



Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002



Energy Range eV



Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF


Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF


WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF



WorkSubwork4

0305004



Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

Slide 14

Slide 15

Slide 16

Slide 17

Slide 18

Slide 19

Slide 20

Slide 21

Slide 22

Slide 23

Slide 24

Slide 25

Slide 26

Slide 27

Slide 28

Slide 29

Slide 30

Slide 31

Slide 32

Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43



lib t n f

ENDF B-VI8 004684 000124 004530 000030

JEFF 30 004018 000055 003943 000021

JENDL 33 005012 000120 004858 000034

BROND 2 004849 000136 004691 000023

CENDL 21 004684 000124 004530 000030

1 2 3 4 5 6

00

02

p(x

)

x = n lt n gt


ENDFB - VI8


1 2 3 4 5000

005

010

015

P(x

)

x = D lt D gt

Wigner distribution

ENDF B - VI


lt D gt = 078747 eV













Energy Range

eV



Experimental Data

of Ref Remarks

104E4-23E5



Maxon Rae plus Liq

Scintillator


1980



686E-1 ndash 15E5


Leibniz weighting)

LINAC GELINA ToF

C6D6

Liq Scintillator


1985

CrossSection


128- 149 E2


LINACSaclay ToF




1975

Res WidthsWork

Subwor20415-005

10E-2- 5E5


LINACHarwellToF

Liq Scintillator

tank



-22E- 494E


LINACORELA ToF

Liq Scintillator

NE226

7-5 RP7 Weston1976



Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002



Energy Range eV



Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF


Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF


WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF



WorkSubwork4

0305004



Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

Slide 14

Slide 15

Slide 16

Slide 17

Slide 18

Slide 19

Slide 20

Slide 21

Slide 22

Slide 23

Slide 24

Slide 25

Slide 26

Slide 27

Slide 28

Slide 29

Slide 30

Slide 31

Slide 32

Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43













Energy Range

eV



Experimental Data

of Ref Remarks

104E4-23E5



Maxon Rae plus Liq

Scintillator


1980



686E-1 ndash 15E5


Leibniz weighting)

LINAC GELINA ToF

C6D6

Liq Scintillator


1985

CrossSection


128- 149 E2


LINACSaclay ToF




1975

Res WidthsWork

Subwor20415-005

10E-2- 5E5


LINACHarwellToF

Liq Scintillator

tank



-22E- 494E


LINACORELA ToF

Liq Scintillator

NE226

7-5 RP7 Weston1976



Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002



Energy Range eV



Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF


Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF


WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF



WorkSubwork4

0305004



Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

Slide 14

Slide 15

Slide 16

Slide 17

Slide 18

Slide 19

Slide 20

Slide 21

Slide 22

Slide 23

Slide 24

Slide 25

Slide 26

Slide 27

Slide 28

Slide 29

Slide 30

Slide 31

Slide 32

Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43

Energy Range

eV



Experimental Data

of Ref Remarks

984E-3 ndash 377E5


ToF LINAC-ORELA

Liq Scintillator

NE226

5-7 CS4968 Weston1975

CrossSectionWork

Subwork 10767-002



Energy Range eV



Uncert

Experimental Data

of Ref Rem

785e-1 108e+3


LINACSaclay ToF


Ne226 for neutrons

2 - 5 CS13840 Derrien1975

WorkSubwork2

0415003

450e+5 248e+7

LINACLL ToF


WorkSubwork

10763002

212e-2 399e+2

Abs Measurement

Reactor ToF



WorkSubwork4

0305004



Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

Slide 14

Slide 15

Slide 16

Slide 17

Slide 18

Slide 19

Slide 20

Slide 21

Slide 22

Slide 23

Slide 24

Slide 25

Slide 26

Slide 27

Slide 28

Slide 29

Slide 30

Slide 31

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Slide 33

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Slide 36

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Slide 38

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Slide 40

Slide 41

Slide 42

Slide 43


Vanpraet et al




Weston amp Todd




























Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

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Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43




















Weston et al

September 96



Nakagawa et al

January 2002















BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

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Slide 32

Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43










BROND vs JENDL 33





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

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Slide 13

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Slide 31

Slide 32

Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43





lib t n f

ENDF B-VI8 004152 000236 003903 134949E-4

JEF

JENDL 33 004521 000193 004307 210834E-4

BROND 2 003941 000233 003697 1293E-4

CENDL 21



04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

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Slide 11

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Slide 13

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Slide 40

Slide 41

Slide 42

Slide 43


04 06 08 10 12 14 16 18 200

10

20

30

40

50

60

Nu

mb

er

of

res

on

an

ce

s



= 43067meV


00 05 10 15 20 25 30 35 40000

006

012

018


p(x

)

x = D lt D gt



lt D gt = 010566meV

1 2 3 4 5 6000

005

010

015

p(x)

xn

n



n gt = 01854meV



Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

Slide 14

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Slide 20

Slide 21

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Slide 28

Slide 29

Slide 30

Slide 31

Slide 32

Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43

Energy Range eV



Uncert

Experimental Data

of Ref Rem


NE213

Van de Graaff ToF

FZK Karlsruhe


5 -20 CSR16CS16

Wisshak et al

983e-1 - 199e1


ToF



WorkSubwork204

15003


ToF



Simpson et al1974

WorkSubwork102

04004


ToF



Simpson et al1974

WorkSubwork102

04004
















data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

Slide 14

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Slide 33

Slide 34

Slide 35

Slide 36

Slide 37

Slide 38

Slide 39

Slide 40

Slide 41

Slide 42

Slide 43














data

ARE HIGHLY NEEDED




Slide 1

Slide 2

Slide 3

Slide 4

Slide 5

Slide 6

Slide 7

Slide 8

Slide 9

Slide 10

Slide 11

Slide 12

Slide 13

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Slide 1

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Nuclear Data for Transmutation: status, needs and methods Review of the available experimental and...

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Transcript of Nuclear Data for Transmutation: status, needs and methods Review of the available experimental and...