A Dosimetry and Visualization Tool for the Fukushima Daiichi … · 2011-04-11 · Artist rendition...

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A A DosimetryDosimetry and Visualization Tool for the and Visualization Tool for the

Fukushima Daiichi Power PlantFukushima Daiichi Power Plant

Justin Vazquez, Justin Vazquez, AipingAiping Ding, Ding, TianyuTianyu Liu, Chao Liang, Benjamin Liu, Chao Liang, Benjamin Lawrence, Christopher Gaylord, and Lin SuLawrence, Christopher Gaylord, and Lin Su

Advisor: Dr. X. George Advisor: Dr. X. George XuXu

Rensselaer Polytechnic InstituteRensselaer Polytechnic Institute

Spring, 2011Spring, 2011

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MotivationMotivation

Fukushima Daiichi Power Plant before and after the disaster

Photos courtesy of The New York Times

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Project ObjectivesProject Objectives

�� Develop a 3Develop a 3--D model of the Fukushima Daiichi D model of the Fukushima Daiichi

Plant and use this model to simulate the events Plant and use this model to simulate the events

of March/April, 2011 using VR and MCNPof March/April, 2011 using VR and MCNP

�� Incorporate into the model such elements as:Incorporate into the model such elements as:

�� Atmospheric dispersion Atmospheric dispersion

�� Radiation sources present through out the incidentRadiation sources present through out the incident

�� Human phantom models for Human phantom models for dosimetrydosimetry calculationcalculation

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Task GroupsTask Groups

1.1. Plant CAD Modeling and VR IntegrationPlant CAD Modeling and VR Integration

�� Justin Vazquez and Justin Vazquez and AipingAiping DingDing

2.2. Reactor Analysis and Source DefinitionReactor Analysis and Source Definition

�� Chao Liang and Chao Liang and TianyuTianyu LiuLiu

3.3. MCNP Simulation DevelopmentMCNP Simulation Development

�� TianyuTianyu Liu and Lin SuLiu and Lin Su

4.4. Atmospheric Dispersion ModelingAtmospheric Dispersion Modeling

�� Benjamin Lawrence and Christopher GaylordBenjamin Lawrence and Christopher Gaylord

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CAD Models of the Fukushima CAD Models of the Fukushima

Daiichi PlantDaiichi Plant

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CAD ModelsCAD Models

�� Two models developedTwo models developed

�� Reactor site model for VR visualizationReactor site model for VR visualization

�� Simplified model for interpretation into code for Simplified model for interpretation into code for

MCNP simulationMCNP simulation

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CAD Model for VR VisualizationCAD Model for VR Visualization

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Aerial View of the Fukushima Daiichi Power Plant (provided by from Google Maps)

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3D Model of the Fukushima Daiichi Power Plant (originally developed/provided by turbosquid.com)

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3D Model of the Fukushima Daiichi Power Plant (working version in CAD)

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Artist rendition of a MARK-I BWR reactor

(courtesy NRC)

3D model based on artist rendition

(developed/provided by turbosquid.com)

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(courtesy NRC)



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(courtesy NRC)



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3-D visual model developed to illustrate steam turbine generator

Photo courtesy of dailykos.com

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Placement of the reactor and turbine objects in full reactor CAD model

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Virtual Reality IntegrationVirtual Reality Integration

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Creating the EON ApplicationCreating the EON Application

CAD

Models

EON

Professional

EON

Applications

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The steps in EON Studio when building all EON The steps in EON Studio when building all EON

applications but the work procedure may also applications but the work procedure may also

include other tasks, for example writing scriptsinclude other tasks, for example writing scripts

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Integration of CAD Models and Integration of CAD Models and

Human Phantom into EONHuman Phantom into EON

Video available on RPI RMDG website:

http://www.rpi.edu/dept/radsafe/public_html/images/RPIfukushima.mp4

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CAD Model for MCNP SimulationCAD Model for MCNP Simulation

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CAD Model for MCNP CAD Model for MCNP

SimulationSimulation

Geometry Simplification for MCNP surface/cell production

(original model developed/provided by turbosquid.com)

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Geometry Simplification for MCNP surface/cell production

(original model developed/provided by turbosquid.com)

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Placement of reactors on map in CAD

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Addition of other plant buildings and ground features

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Completed CAD model for MCNP simulation

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Completed CAD model for MCNP simulation

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Verifying MCNP ResultsVerifying MCNP Results

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Result VerificationResult Verification

Dose distribution measurements will be compared with measurements provided by NISA.

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Result VerificationResult Verification

Dose distribution measurements will be compared with measurements provided by NISA.

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Reactor and Radiation Reactor and Radiation

Source Analysis Source Analysis

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Fukushima Daiichi Reactor Basic InfoFukushima Daiichi Reactor Basic InfoUnitUnit Reactor Reactor

typetype

# Core fuel # Core fuel

assembliesassemblies

PowerPower

[[MWe/MWthMWe/MWth]]

Fuel Fuel

TypeType

Uranium Uranium

Load [ton]Load [ton]

# Spent fuel # Spent fuel

assembliesassemblies

11 BWRBWR--33 400400460/1380460/1380 LEULEU 6969 292292

22 BWRBWR--44 548548784/2381784/2381 LEULEU 9494 587587

33 BWRBWR--44 548548784/2381784/2381 MOXMOX

LEULEU

9494 514514

44 BWRBWR--44 00784/2381784/2381 LEULEU 9494 13311331

55 BWRBWR--44 548548784/2381784/2381 LEULEU 9494 946946

66 BWRBWR--55 7647641100/32931100/3293 LEULEU 132132 876876

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DaiichiDaiichi--3 Core Radioactivity3 Core Radioactivity

Isotope Activity Isotope Activity Isotope Activity

11140140BaBa 39.939.9 1212

85m85mKrKr 5.75.7 23239090SrSr 1.61.6

22144144CeCe 27.927.9 1313

8787KrKr 7.97.9 24249191SrSr 30.030.0

33134134CsCs 62.762.7 1414

8888KrKr 14.814.8 2525129m129mTeTe 1.21.2

44136136CsCs 0.40.4 1515

140140LaLa 40.340.3 2626131m131mTeTe 3.53.5

55137137CsCs 1.91.9 1616

9999MoMo 39.739.7 2727132132TeTe 29.729.7

66131131II 20.520.5 1717

239239NpNp 412.0412.0 2828131m131mXeXe 0.20.2

77132132II 30.230.2 1818

103103RuRu 27.627.6 2929133133XeXe 44.344.3

88133133II 43.543.5 1919

106106RuRu 6.16.1 3030133m133mXeXe 1.41.4

99134134II 36.436.4 2020

127127SbSb 1.41.4 3131135135XeXe 26.226.2

1010135135II 37.637.6 2121

129129SbSb 5.35.3 3232138138XeXe 2.12.1

11118585KrKr 0.20.2 2222

8989SrSr 26.126.1 33339191YY 32.732.7

All values are obtained form SCALE/ORIGEN in unit of [million Curie]

at the moment of shutdown.

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Gamma Spectra Gamma Spectra hourhour--byby--hourhour

Decay information source: Berkeley Laboratory Isotopes Project, Korea Atomic Energy Research Institute

NuclideNuclide HalfHalf--LifeLife

II--131131 8 days8 days

CsCs--137137 30 years30 years

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Source Card used in MCNPSource Card used in MCNP

�� Assumptions according to the events and Assumptions according to the events and

damage happened to the power plantsdamage happened to the power plants

1) Percentage of radionuclide released;1) Percentage of radionuclide released;

2) The release pathway.2) The release pathway.

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Radiation Release Events at the Radiation Release Events at the

Fukushima Daiichi PlantFukushima Daiichi Plant

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Overview of EventsOverview of Events

�� 3/113/11--14:46 14:46 EarthquakeEarthquake

�� Units 1Units 1--3: SCRAM3: SCRAM

�� Units 4Units 4--6: not operating6: not operating

�� Emergency Core Cooling SystemEmergency Core Cooling System

--15:41 15:41 TsunamiTsunami

�� Diesel generator damagedDiesel generator damaged

�� Reactor Core Isolation Reactor Core Isolation

Cooling SystemCooling System

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Turbine

Pump

Wet-well (Torus for Mark I)

CST

RCIC—battery

Diagram courtesy of NRC

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Safety/relief valves

�Residual heat

�steam�pressure

�Safety relief valves manually/automatically opened

Diagram courtesy of scribid.com

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Overview of EventsOverview of Events�Fuel damage�Core uncovery

�Fuel ballooning & bursting

�Rapid Oxidation�Zr+ 2H2O=ZrO2+2H2 @1500K

�P(oxid)>P(decay)

�Debris bed formation�Zr+UO2 melt@1700K

Plate-out

Fission product, noble

gases(Xe, Kr), H2

Diagram courtesy of scribid.com

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Overview of EventsOverview of EventsService Floor

�Primary Containment Depressurization

3/12-14:30 Start venting U1.

-20:41 Starting venting U3.


-11:00 Start venting U2.


3/15-00:02 Start venting U2 again. Diagram courtesy of scribid.com

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�� Hydrogen ExplosionHydrogen Explosion�� 2H2H22+O+O22 =2H=2H22OO

�� 3/123/12--15:36 U1 @ service building15:36 U1 @ service building

�� 3/143/14--11:01 U3 @ service building11:01 U3 @ service building

�� 3/153/15--06:10 U2 @ torus wet06:10 U2 @ torus wet--well (suspected)well (suspected)

�� 3/153/15--06:00 U4 @ SFP (reported by JAIF)06:00 U4 @ SFP (reported by JAIF)

Instant release

Photos courtesy of The New York Times

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�� Steam/SmokeSteam/Smoke

�� 3/153/15--08:25 White smoke at U2.08:25 White smoke at U2.

�� 3/163/16--08:34 and 08:34 and --10:00 White smoke from U3.10:00 White smoke from U3.

�� 3/213/21--18:22 White vapor (steam) erupted at U218:22 White vapor (steam) erupted at U2

--15:55~18:02 Gray smoke erupted at U3.15:55~18:02 Gray smoke erupted at U3.

�� 3/273/27--White vapor (steam) from U2, U3, and U4.White vapor (steam) from U2, U3, and U4.


Stable release

Photo courtesy of en.trend.az

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Atmospheric Dispersion ModelingAtmospheric Dispersion Modeling

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Atmospheric Dispersion Modeling:Atmospheric Dispersion Modeling:

Task ObjectivesTask Objectives

�� Model that predicts distribution of radioactive Model that predicts distribution of radioactive

plume as function of time and location off siteplume as function of time and location off site

1.1. Deposition on ground of CsDeposition on ground of Cs--137 and I137 and I--131 in local 131 in local

area of Japanarea of Japan

2.2. Concentration, from ground up to 2 meters, of Concentration, from ground up to 2 meters, of

released radioactivityreleased radioactivity

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Dispersion of Gas from a Continuous Source:Dispersion of Gas from a Continuous Source:

PasquillPasquill--Gifford equation (Gaussian Plume Model)Gifford equation (Gaussian Plume Model)

�� χχ == Q *Q *[[--0.5(0.5(yy22//σσyy22 + H+ Hee

22//σσzz22)] / ()] / (πσπσyyσσzzµµ))

�� HHee==HHss+d(v+d(v//µµ))1.41.4(1+(1+∆∆T/T)T/T)

Source: Chapter 11 from Introduction to Health Physics by Cember and Johnson

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HYSPLIT ModelHYSPLIT Model�� Model utilized: Hybrid Single Particle Model utilized: Hybrid Single Particle LagrangianLagrangian Integrated Integrated

Trajectory Model Trajectory Model (HYSPLIT)(HYSPLIT)

�� Produced by National Oceanic and Atmospheric Administration (NOAProduced by National Oceanic and Atmospheric Administration (NOAA) A)

and Australian Bureau of Meteorologyand Australian Bureau of Meteorology

�� Uses National Weather ServiceUses National Weather Service’’s (NWS) Global Data Assimilation s (NWS) Global Data Assimilation

System (GDAS)System (GDAS)

�� Accurate (1Accurate (1oo lat/long, 3 hr timeframe)lat/long, 3 hr timeframe)

�� Can provide trajectory, concentration, Can provide trajectory, concentration,

dispersion, and exposure modelingdispersion, and exposure modeling

�� PrePre--programmed Csprogrammed Cs--137 and I137 and I--131131

Photo courtesy of NOAA

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HYSPLIT SimulationsHYSPLIT Simulations

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Local Radioactivity Distribution Local Radioactivity Distribution


Concentration [µCi/m3] in air from March 14th to March 17th

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Local Radioactivity Distribution Local Radioactivity Distribution


Deposition [µCi/m2] on ground from March 14th to March 17th

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Global Radioactivity Distribution Global Radioactivity Distribution


Concentration [µCi/m3] in air from March 14th to March 21st

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Results from PreliminaryResults from Preliminary

MCNP Simulations MCNP Simulations

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Geometry SimplificationGeometry Simplification

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Simulation 1 Simulation 1 –– AssumptionsAssumptions

�� Secondary containment Secondary containment

for all reactors intactfor all reactors intact

�� Damage to primary Damage to primary

containment in Units 1containment in Units 1--44

�� Uniformly distributed Uniformly distributed

CsCs--137 inside of 137 inside of

secondary containmentsecondary containment

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for all reactors intactfor all reactors intact

�� Damage to primary Damage to primary

containment in Units 1containment in Units 1--44




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Simulation Simulation –– Tally DefinitionTally Definition

�� Type 1 mesh tally in MCNPX ver. 2.5.0Type 1 mesh tally in MCNPX ver. 2.5.0

�� Modified to calculateModified to calculate equivalent dose in tissue/organ equivalent dose in tissue/organ

�� Mesh size: Mesh size:

�� 1010××1010××10m cube10m cube

�� Tallied area: Tallied area:

�� X: X: --10m 10m -- 900m900m

�� Y: Y: --80m 80m -- 1200m1200m

�� Z: 0m Z: 0m -- 10m10m

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Simulation 1 Simulation 1 –– ResultsResults

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damaged for Units 1damaged for Units 1--44

�� Roofs partially removedRoofs partially removed

�� Release of radioactivityRelease of radioactivity




�� Cylindrical source: Cylindrical source:

R=10m, H=150mR=10m, H=150m

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Simulation 2 Simulation 2 –– ResultsResults

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Conclusions & Further WorkConclusions & Further Work

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What WeWhat We’’ve Learned so Farve Learned so Far

�� Geometry simplification an effective method for Geometry simplification an effective method for

MCNP simulationMCNP simulation

�� Proper defining of the source term perhaps the Proper defining of the source term perhaps the

most important aspect of simulationmost important aspect of simulation

�� Must accurately depict distribution of Must accurately depict distribution of radionuclidesradionuclides

over timeover time

�� Methods detailed in the present study could be Methods detailed in the present study could be

powerful tool for simulating and planning for powerful tool for simulating and planning for

emergency situationsemergency situations

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Next StagesNext Stages

�� Translation of CAD Model into MCNPTranslation of CAD Model into MCNP

�� Performed either through the use of the MCAM Performed either through the use of the MCAM

CADCAD--toto--MCNP software, or manual cell definitionMCNP software, or manual cell definition

�� Improvement of source termImprovement of source term

�� Improved estimates of radioactive nuclide releaseImproved estimates of radioactive nuclide release

�� Accounting for localized atmospheric dispersionAccounting for localized atmospheric dispersion

�� Accounting for radiation from spent fuel poolsAccounting for radiation from spent fuel pools

�� Use of varianceUse of variance--reduction techniques in MCNPreduction techniques in MCNP

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Further WorkFurther Work

�� Integration of dose distribution estimates with Integration of dose distribution estimates with

VR interfaceVR interface

�� Informative, interactive VR simulationInformative, interactive VR simulation

�� Determination of dose in human phantomsDetermination of dose in human phantoms

�� Simulation of impact on workers affected by the Simulation of impact on workers affected by the

incidentincident

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Future DirectionsFuture Directions

�� Simulation of radiation events using Google Simulation of radiation events using Google Earth imagery to model major cities in the U.S.Earth imagery to model major cities in the U.S.

�� Example: New York CityExample: New York City

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Future DirectionsFuture Directions

�� Simulation of individuals walking and sitting on Simulation of individuals walking and sitting on contaminated groundcontaminated ground�� CsCs--137 and Co137 and Co--60 with concentrations of 30 60 with concentrations of 30 kBqkBq mm--22

�� Parallel and isotropic planar sourcesParallel and isotropic planar sources

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Special ThanksSpecial Thanks

�� Rensselaer Nuclear Engineering facultyRensselaer Nuclear Engineering faculty

�� Dr. Peter Dr. Peter CaracappaCaracappa

�� Dr. Dr. SastrySastry SreepadaSreepada

�� Dr. Dr. YaronYaron DanonDanon

�� Rensselaer Nuclear Engineering studentsRensselaer Nuclear Engineering students

�� Matthew MilleMatthew Mille

�� RianRian BahranBahran

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Please contact Justin Vazquez of the RPI Please contact Justin Vazquez of the RPI

Radiation Measurement and Radiation Measurement and DosimetryDosimetry Group to Group to

attain a copy of any of the simulation videos attain a copy of any of the simulation videos

discussed in this presentation: discussed in this presentation: [email protected]@rpi.edu

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