a dosimetry and visualization tool for the fukushima daiichi power plant

7/31/2019 A Dosimetry and Visualization Tool for the Fukushima Daiichi Power Plant

1/68

1

AADosimetryDosimetry and Visualization Tool for theand Visualization Tool for the

Fukushima Daiichi Power PlantFukushima Daiichi Power Plant

Justin Vazquez,Justin Vazquez,AipingAipingDing,Ding,TianyuTianyu Liu, Chao Liang, BenjaminLiu, Chao Liang, BenjaminLawrence, Christopher Gaylord, and Lin SuLawrence, Christopher Gaylord, and Lin Su

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

Rensselaer Polytechnic InstituteRensselaer Polytechnic Institute

Spring, 2011Spring, 2011


2/68

2

MotivationMotivation

Fukushima Daiichi Power Plant before and after the disaster

Photos courtesy of The New York Times


3/68

3

Project ObjectivesProject Objectives

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

Plant and use this model to simulate the eventsPlant and use this model to simulate the eventsof 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 dispersionAtmospheric dispersion

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

Human phantom models forHuman phantom models for dosimetrydosimetrycalculationcalculation


4/68


5/68

5

CAD Models of the FukushimaCAD Models of the Fukushima

Daiichi PlantDaiichi Plant


6/68

6

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 forSimplified model for interpretation into code for

MCNP simulationMCNP simulation


7/68

7

CAD Model for VR VisualizationCAD Model for VR Visualization


8/68

8


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


9/68

9


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


10/68

10


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


11/68

11


Artist rendition of a MARK-I BWR reactor

(courtesy NRC)

3D model based on artist rendition

(developed/provided by turbosquid.com)


12/68

12



(courtesy NRC)




13/68

13



(courtesy NRC)




14/68

14


3-D visual model developed to illustrate steam turbine generator

Photo courtesy of dailykos.com


15/68

15


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


16/68

16




17/68

17




18/68

18

Virtual Reality IntegrationVirtual Reality Integration


19/68

19

Creating the EON ApplicationCreating the EON Application

CAD

Models

EON

Professional

EON

Applications


20/68

20

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

applications but the work procedure may alsoapplications but the work procedure may alsoinclude other tasks, for example writing scriptsinclude other tasks, for example writing scripts


21/68

21

Integration of CAD Models andIntegration 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


22/68


23/68

23

CAD Model for MCNPCAD Model for MCNP

SimulationSimulation

Geometry Simplification for MCNP surface/cell production(original model developed/provided by turbosquid.com)


24/68

24



Geometry Simplification for MCNP surface/cell production(original model developed/provided by turbosquid.com)


25/68

25



Placement of reactors on map in CAD


26/68

26



Addition of other plant buildings and ground features


27/68

27



Completed CAD model for MCNP simulation


28/68

28



Completed CAD model for MCNP simulation


29/68

29

Verifying MCNP ResultsVerifying MCNP Results


30/68

30

Result VerificationResult Verification

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


31/68

31

Result VerificationResult Verification

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


32/68

32

Reactor and RadiationReactor and Radiation

Source AnalysisSource Analysis


33/68

33

Fukushima Daiichi Reactor Basic InfoFukushima Daiichi Reactor Basic InfoUnitUnit ReactorReactor

typetype

# Core fuel# Core fuel

assembliesassemblies

PowerPower

[[MWe/MWthMWe/MWth]]

FuelFuel

TypeType

UraniumUranium

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


34/68

34

DaiichiDaiichi--3 Core Radioactivity3 Core Radioactivity

Isotope Activity Isotope Activity Isotope Activity11

140140BaBa 39.939.9 1212 85m85mKrKr 5.75.7 2323 9090SrSr 1.61.6

22144144CeCe 27.927.9 1313 8787KrKr 7.97.9 2424 9191SrSr 30.030.0

33134134CsCs 62.762.7 1414 8888KrKr 14.814.8 2525 129m129mTeTe 1.21.2

44 136136CsCs 0.40.4 1515 140140LaLa 40.340.3 2626 131m131mTeTe 3.53.555

137137CsCs 1.91.9 1616 9999MoMo 39.739.7 2727 132132TeTe 29.729.7

66131131II 20.520.5 1717 239239NpNp 412.0412.0 2828 131m131mXeXe 0.20.2

77132132II 30.230.2 1818 103103RuRu 27.627.6 2929 133133XeXe 44.344.3

88 133133II 43.543.5 1919 106106RuRu 6.16.1 3030 133m133mXeXe 1.41.4

99134134II 36.436.4 2020 127127SbSb 1.41.4 3131 135135XeXe 26.226.2

1010135135II 37.637.6 2121 129129SbSb 5.35.3 3232 138138XeXe 2.12.1

11118585KrKr 0.20.2 2222 8989SrSr 26.126.1 3333 9191YY 32.732.7

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

at the moment of shutdown.


35/68

35

Gamma SpectraGamma 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


36/68

36

Source Card used in MCNPSource Card used in MCNP Assumptions according to the events andAssumptions according to the events and

damage happened to the power plantsdamage happened to the power plants1) Percentage of radionuclide released;1) Percentage of radionuclide released;

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


37/68

37

Radiation Release Events at theRadiation Release Events at the

Fukushima Daiichi PlantFukushima Daiichi Plant


38/68

38

Overview of EventsOverview of Events 3/113/11--14:4614:46 EarthquakeEarthquake

Units 1Units 1--3: SCRAM3: SCRAM Units 4Units 4--6: not operating6: not operating

Emergency Core Cooling SystemEmergency Core Cooling System

--15:4115:41TsunamiTsunami

Diesel generator damagedDiesel generator damaged

Reactor Core IsolationReactor Core IsolationCooling SystemCooling System


39/68

39

Overview of EventsOverview of Events

Turbine

Pump

Wet-well (Torus for Mark I)

CST

RCICbattery

Diagram courtesy of NRC


40/68

40

Overview of EventsOverview of EventsSafety/relief valves

Residual heatsteampressure

Safety relief valvesmanually/automatically

opened

Diagram courtesy of scribid.com


41/68

41

Overview of EventsOverview of EventsFuel damageCore uncovery

Fuel ballooning & burstingRapid OxidationZr+ 2H2O=ZrO2+2H2 @1500KP(oxid)>P(decay)

Debris bed formationZr+UO2 melt@1700K

Plate-out

Fission product, noblegases(Xe, Kr), H2

Diagram courtesy of scribid.com


42/68

42

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


43/68

43

Overview of EventsOverview of Events 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


44/68

44

Steam/SmokeSteam/Smoke

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

3/163/16--08:34 and08:34 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.

Overview of EventsOverview of Events

Stable release

Photo courtesy of en.trend.az


45/68

45

Atmospheric Dispersion ModelingAtmospheric Dispersion Modeling

A h i Di i M d liA h i Di i M d li


46/68

46

Atmospheric Dispersion Modeling:Atmospheric Dispersion Modeling:

Task ObjectivesTask Objectives

Model that predicts distribution of radioactiveModel that predicts distribution of radioactiveplume 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 local131 in local

area of Japanarea of Japan2.2. Concentration, from ground up to 2 meters, ofConcentration, from ground up to 2 meters, of

released radioactivityreleased radioactivity


47/68

47

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)

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

22//zz22)] / ()] / (yyzz))

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

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


48/68

48

HYSPLIT ModelHYSPLIT Model Model utilized: Hybrid Single ParticleModel utilized: Hybrid Single Particle LagrangianLagrangian IntegratedIntegrated

Trajectory ModelTrajectory 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 Services (NWS) Global Data Assimilations (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


49/68

49

HYSPLIT SimulationsHYSPLIT Simulations

L l R di i i Di ib iL l R di i i Di ib i


50/68

5050

Local Radioactivity DistributionLocal Radioactivity Distribution

SimulationSimulationConcentration [Ci/m3] in air from March 14th to March 17th

L l R di i i Di ib iL l R di ti it Di t ib ti


51/68

5151

Local Radioactivity DistributionLocal Radioactivity Distribution

SimulationSimulationDeposition [Ci/m2] on ground from March 14th to March 17th

Gl b l R di ti it Di t ib tiGlobal Radioacti it Distrib tion


52/68

5252

Global Radioactivity DistributionGlobal Radioactivity Distribution

SimulationSimulationConcentration [Ci/m3] in air from March 14th to March 21st


53/68

53

Results from PreliminaryResults from Preliminary

MCNP SimulationsMCNP Simulations


54/68

54

Geometry SimplificationGeometry Simplification


55/68

55

Simulation 1Simulation 1AssumptionsAssumptions Secondary containmentSecondary containment

for all reactors intactfor all reactors intact Damage to primaryDamage to primary

containment in Units 1containment in Units 1--44

Uniformly distributedUniformly distributed

CsCs--137 inside of137 inside of

secondary containmentsecondary containment


56/68

56


for all reactors intactfor all reactors intact Damage to primaryDamage to primary

containment in Units 1containment in Units 1--44





57/68

57

SimulationSimulationTally 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/organequivalent dose in tissue/organ Mesh size:Mesh size:

1010101010m cube10m cube

Tallied area:Tallied area:

X:X: --10m10m -- 900m900m

Y:Y: --80m80m -- 1200m1200m Z: 0mZ: 0m -- 10m10m


58/68

58

Simulation 1Simulation 1ResultsResults


59/68

59


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


60/68

60

Simulation 2Simulation 2ResultsResults


61/68

61

Conclusions & Further WorkConclusions & Further Work


62/68

62

What WeWhat Weve Learned so Farve Learned so Far Geometry simplification an effective method forGeometry simplification an effective method for

MCNP simulationMCNP simulation Proper defining of the source term perhaps theProper defining of the source term perhaps the

most important aspect of simulationmost important aspect of simulation

Must accurately depict distribution ofMust accurately depict distribution ofradionuclidesradionuclides

over timeover time

Methods detailed in the present study could beMethods detailed in the present study could bepowerful tool for simulating and planning forpowerful tool for simulating and planning for

emergency situationsemergency situations


63/68

63

Next StagesNext Stages Translation of CAD Model into MCNPTranslation of CAD Model into MCNP

Performed either through the use of the MCAMPerformed either through the use of the MCAMCADCAD--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


64/68

64

Further WorkFurther Work Integration of dose distribution estimates withIntegration 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 theSimulation of impact on workers affected by the

incidentincident


65/68

65

Future DirectionsFuture Directions Simulation of radiation events using GoogleSimulation 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


66/68

66

Future DirectionsFuture Directions Simulation of individuals walking and sitting onSimulation of individuals walking and sitting on

contaminated groundcontaminated ground CsCs--137 and Co137 and Co--60 with concentrations of 3060 with concentrations of 30 kBqkBqmm--22

Parallel and isotropic planar sourcesParallel and isotropic planar sources


67/68

67

Special ThanksSpecial Thanks Rensselaer Nuclear Engineering facultyRensselaer Nuclear Engineering faculty

Dr. PeterDr. Peter CaracappaCaracappa Dr.Dr. SastrySastrySreepadaSreepada

Dr.Dr.YaronYaron DanonDanon

Rensselaer Nuclear Engineering studentsRensselaer Nuclear Engineering students

Matthew MilleMatthew Mille

RianRian BahranBahran


68/68

68

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

Radiation Measurement andRadiation Measurement and DosimetryDosimetryGroup toGroup toattain a copy of any of the simulation videosattain a copy of any of the simulation videos

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

a dosimetry and visualization tool for the fukushima daiichi power plant

Documents