Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application (Woodhead Publishing Series in Energy) PDF
Preview Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application (Woodhead Publishing Series in Energy)
NUCLEAR POWER PLANT DESIGN AND ANALYSIS CODES Woodhead Publishing Series in Energy NUCLEAR POWER PLANT DESIGN AND ANALYSIS CODES Development, Validation, and Application Edited by J W UN ANG X L IN I C A HRIS LLISON J H UDY OHORST WoodheadPublishingisanimprintofElsevier TheOfficers’MessBusinessCentre,RoystonRoad,Duxford,CB224QH,UnitedKingdom 50HampshireStreet,5thFloor,Cambridge,MA02139,UnitedStates TheBoulevard,LangfordLane,Kidlington,OX51GB,UnitedKingdom Copyright©2021ElsevierLtd.Allrightsreserved. Nopartofthispublicationmaybereproducedortransmittedinanyformorbyanymeans,electronicormechanical, includingphotocopying,recording,oranyinformationstorageandretrievalsystem,withoutpermissioninwritingfromthe publisher.Detailsonhowtoseekpermission,furtherinformationaboutthePublisher’spermissionspoliciesandour arrangementswithorganizationssuchastheCopyrightClearanceCenterandtheCopyrightLicensingAgency,canbefound atourwebsite:www.elsevier.com/permissions. ThisbookandtheindividualcontributionscontainedinitareprotectedundercopyrightbythePublisher(otherthanasmay benotedherein). Notices Knowledgeandbestpracticeinthisfieldareconstantlychanging.Asnewresearchandexperiencebroadenour understanding,changesinresearchmethods,professionalpractices,ormedicaltreatmentmaybecomenecessary. Practitionersandresearchersmustalwaysrelyontheirownexperienceandknowledgeinevaluatingandusingany information,methods,compounds,orexperimentsdescribedherein.Inusingsuchinformationormethodstheyshouldbe mindfuloftheirownsafetyandthesafetyofothers,includingpartiesforwhomtheyhaveaprofessionalresponsibility. Tothefullestextentofthelaw,neitherthePublishernortheauthors,contributors,oreditors,assumeanyliabilityforany injuryand/ordamagetopersonsorpropertyasamatterofproductsliability,negligenceorotherwise,orfromanyuseor operationofanymethods,products,instructions,orideascontainedinthematerialherein. BritishLibraryCataloguing-in-PublicationData AcataloguerecordforthisbookisavailablefromtheBritishLibrary LibraryofCongressCataloging-in-PublicationData AcatalogrecordforthisbookisavailablefromtheLibraryofCongress ISBN:978-0-12-818190-4(print) ISBN:978-0-12-818191-1(online) ForinformationonallWoodheadPublishingpublications visitourwebsiteathttps://www.elsevier.com/books-and-journals Publisher:CandiceJanco AcquisitionEditor:MariaConvey EditorialProjectManager:LeticiaM.Lima ProductionProjectManager:AnithaSivaraj CoverDesigner:MatthewLimbert TypesetbyMPSLimited,Chennai,India Contents List of contributors ix 3.5 Summary 72 References 72 I 4. Multiphysics coupling plan Map of code development MiaoGuiandXingangZhao 4.1 Introduction 75 1. Road map 4.2 Multiphysicscouplingmethods 76 LinSun,XiaomengDong,XinLi,JunWangandKayaG.Mondry 4.3 Currentstatusofresearchinmultiphysics coupling 82 1.1 Overview 3 4.4 Conclusion 93 1.2 Fuelcodes 5 References 93 1.3 Systemcode 6 1.4 Subchannelanalysiscode 10 1.5 Computationalfluiddynamicscode 12 II 1.6 Coupledmultiscalethermal-hydraulics codes 14 Physics and fuels codes 1.7 EmergingmethodsforNPPs 16 References 18 5. Nuclear physics deterministic code 2. Guidance of nuclear power plant code TengfeiZhang development 5.1 Nucleardataprocessingcodes 97 XianpingZhong 5.2 Crosssectiongenerationcodes 99 5.3 Whole-corecomputationalcodes 109 2.1 Nuclearpowerplantcode 23 References 115 2.2 Codedevelopmentexamples 27 2.3 Sourcecode 42 6. Nuclear physics probability code: References 53 OpenMC 3. Nuclear engineering software quality JiankaiYu assurance 6.1 IntroductiontoMonteCarlomethod 123 6.2 RecentlydevelopedMonte XingheNi Carlocodes 124 3.1 Introduction 55 6.3 TypicalmethodologiesinOpenMC 125 3.2 Softwaredevelopmentlifecycle 58 6.4 UsageofOpenMC 130 3.3 Softwarequality 64 6.5 Verificationandvalidation 135 3.4 Softwarequalityassurancefornuclear 6.6 Summary 137 engineering 68 References 137 v vi Contents III 10. Subchannel codes: CTF and VIPRE-01 XingangZhao Fuels and sub-channel codes 10.1 IntroductionandCTFcodeoverview 235 7. FRAPCON and FRAPTRAN codes: 10.2 CTFassessment:Motivationandwork Fuel rod performance analysis codes scope 237 10.3 VIPRE-01codeoverview 238 under normal and accident 10.4 CTFassessment:Flowmixing 238 conditions 10.5 CTFassessment:Pressuredrop 243 BowenQiuandJunWang 10.6 CTFassessment:Voidfraction 249 10.7 Summary 255 7.1 Objectives,relations,andlimitations 141 References 257 7.2 Codestructuresandphysicalmodels 143 7.3 Assessments 152 7.4 Summary 158 IV References 159 Thermal-hydraulic codes 8. The TRANSURANUS fuel 11. System-level code TRACE performance code AnilGurgen A.Magni,A.DelNevo,L.Luzzi,D.Rozzia,M.Adorni, A.SchubertandP.VanUffelen 11.1 FeaturesofTRACE 261 8.1 Introduction:Generaloverviewofthe 11.2 ConstitutiveequationsofTRACE 263 TRANSURANUScode 161 11.3 ValidationofTRACE 274 8.2 TRANSURANUScodestructure 162 References 275 8.3 Applicationtowaterreactorconditions 168 8.4 Preliminaryassessmentagainstfastreactor 12. Nuclear thermal hydraulics with the conditions 186 AC2 system code package 8.5 Conclusionsandfuturecode AndreasWielenbergandChristineBals developments 198 Nomenclature 200 12.1 Thesystemthermal-hydrauliccode References 201 ATHLET 277 12.2 COntainmentCOdeSYStemthermal-hydraulic moduleTHY 298 9. Two fuel performance codes of the 12.3 Qualityassurancemeasures 305 PLEIADES platform: ALCYONE and 12.4 Outlookandsummary 305 GERMINAL Nomenclature 306 B.Michel,I.Ramie`re,I.Viallard,C.Introini,M.Lainet, References 307 N.Chauvin,V.Marelle,A.Boulore,T.Helfer,R.Masson,J. Sercombe,J.C.Dumas,L.NoirotandS.Bernaud 13. Development and application of System Analysis Module from the 9.1 GeneraloverviewofthePLEIADESfuel softwareenvironment 207 user’s view 9.2 ALCYONEfuelperformancecodeforGENII YukunZhou,AlejandroPerezandJunWang andIII 210 9.3 GERMINALfuelperformancecodeforGEN 13.1 Introduction 313 IV 224 13.2 Softwaredevelopment 314 9.4 Conclusionandprospects 231 13.3 Verificationanddemonstration 319 Acknowledgment 231 13.4 Integrationandcoupling 330 References 231 References 332 vii Contents 14. Mechanism-based codes for severe 17. Engineering-level system code for accident analysis severe accident analysis: MELCOR LutengZhang TangtaoFeng,JunWang,XinLi,RyanDaileyandGeorgeVayssier 14.1 COPRAcode 333 17.1 Introduction 417 14.2 IVRASAcode 345 17.2 Qualitycontrol 420 14.3 ThermalEXplosionAnalysisSimulation 17.3 Capabilitiesandlimitations 427 code 349 17.4 MELCORversionupdatehistory 429 14.4 MOCOcode 352 17.5 Demonstrationproblems:Experimentsfor 14.5 DETACcode 356 validation 430 References 359 Reference 434 VI V Noval CFD methods Severe accident codes 18. Moving Particle Semi-implicit 15. Severe accident analysis method with AC2 ZidiWang,GuangtaoDuan,SeiichiKoshizukaandAkifumiYamaji AndreasWielenberg,SaraBeck,ThorstenHollands,LiviuszLovasz, HolgerNowack,ClausSpengler,MartinSonnenkalband 18.1 Introduction 439 AndreasSchaffrath 18.2 MovingParticleSemi-implicitmethod 440 15.1 ThesevereaccidentcodeATHLET-CDforin- 18.3 Applicationtonuclearengineering 446 18.4 Conclusion 458 vesselphenomena 363 Reference 458 15.2 Severeaccidentanalysisforcontainment phenomenawithContainmentCode 19. Lattice Boltzmann method code System 378 15.3 Qualityassurancemeasures 389 ShimpeiSaitoandHuiCheng 15.4 Outlookandsummary 390 Nomenclature 391 19.1 Introduction 463 References 392 19.2 LatticeBoltzmannmultiphasemodels 464 19.3 Summary 476 References 476 16. Integral severe accident codes: IMPACT/SAMPSON VII MarcoPellegrini Special or new direction 16.1 Introduction 397 16.2 SAMPSONmainmodules 398 16.3 3Dcontainmentmodules 405 20. Code for nuclear materials 16.4 ApplicationoftheSAMPSONcodetothe JianqiXi FukushimaDaiichinuclearpowerplant accident 410 20.1 Electronicstructurecalculationsinnuclear 16.5 Advantagesanddisadvantagesintheuseof materials 483 SAMPSON 414 20.2 Moleculardynamicssimulationsinnuclear References 414 materials 486 viii Contents 20.3 Mesoscalemodelinginnuclearmaterials 23. New direction of nuclear code field 489 development: artificial intelligence References 492 LianshanLinandXingWang 21. Nuclear power plant cybersecurity 23.1 Introduction 543 FanZhang 23.2 Abriefhistoryofartificialintelligence 544 23.3 Artificialintelligenceresearchinnuclear 21.1 Introduction 495 powerindustryinthe1980s 547 21.2 Cybersecuritydifferencesofinstrumentation 23.4 Recentapplicationofartificialintelligencein andcontrolsystemandinformation nuclearpowerplantcode 548 technologysystem 496 References 550 21.3 Cyber-incidentsinthehistoryofthenuclear industry 497 24. Temporal data mining in nuclear site 21.4 Regulations 499 monitoring and in situ decommissioning 21.5 Cyberattackdetectionresearchusing machine-learningalgorithms 503 Z.J.SunandA.Duncan 21.6 Conclusion 510 24.1 Introduction 553 Acknowledgment 511 24.2 Theoretical:Frequentepisodeanddiscovery References 511 algorithms 554 24.3 Computational:Applicationof 22. Artificial neural network introductions TDMiner 558 JingZhangandGuanghuiSu 24.4 Experimental:InsitudecommissioningSensor NetworkTestBedanddatacollection 571 22.1 Whatisartificialneuralnetwork 515 24.5 Dataanalysisanddiscussions 574 22.2 Theoryofartificialneuralnetwork 516 24.6 Conclusionandfuturework 580 22.3 ArtificialneuralnetworkapplicationsinT/H References 580 problem 522 References 537 Index 583 List of contributors M.Adorni SeniorScientist,Brussels,Belgium Miao Gui School of Nuclear Science and Christine Bals Gesellschaft fu¨r Anlagen- und Technology, Xi’an Jiaotong University, Xi’an, Shaanxi,P.R.China Reaktorsicherheit (GRS) gGmbH, Schwertnergasse,Cologne,Germany Anil Gurgen Department of Nuclear Engineering,North CarolinaState University, Sara Beck Gesellschaft fu¨r Anlagen- und Raleigh,NC,UnitedStates Reaktorsicherheit (GRS) gGmbH, T.Helfer CEA,DES,IRESNE,DEC,Cadarache Schwertnergasse,Cologne,Germany F-13108,Saint-Paul-Lez-Durance,France S. Bernaud CEA, DES, IRESNE, DEC, Thorsten Hollands Gesellschaft fu¨r Anlagen- Cadarache F-13108, Saint-Paul-Lez-Durance, und Reaktorsicherheit (GRS) gGmbH, France Schwertnergasse,Cologne,Germany A.Boulore CEA,DES,IRESNE,DEC,Cadarache C. Introini CEA, DES, IRESNE, DEC, F-13108,Saint-Paul-Lez-Durance,France Cadarache F-13108, Saint-Paul-Lez-Durance, N. Chauvin CEA, DES, IRESNE, DEC, France Cadarache F-13108, Saint-Paul-Lez-Durance, Seiichi Koshizuka Department of Systems France Innovation, The University of Tokyo, Tokyo, Hui Cheng Sino-French Institute of Nuclear Japan Engineering and Technology, Sun Yat-Sen M. Lainet CEA, DES, IRESNE, DEC, University,Zhuhai,P.R.China Cadarache F-13108, Saint-Paul-Lez-Durance, Ryan Dailey Department of Engineering France Physics, University of Wisconsin(cid:1)Madison, Xin Li Faculty of Science and Engineering, Madison,WI,UnitedStates Waseda University, Shinjuku City, Tokyo, A. Del Nevo ENEA, FSN-ING-SIS, CR- Japan Brasimone,Camugnano,Italy Lianshan Lin Materials Science and Xiaomeng Dong Shenzhen University, Technology Division, Oak Ridge National GuangdongProvince,China Laboratory,OakRidge,TN,UnitedStates Guangtao Duan Department of Systems Liviusz Lovasz Gesellschaft fu¨r Anlagen- und Innovation, The University of Tokyo, Tokyo, Reaktorsicherheit (GRS) gGmbH, Japan Schwertnergasse,Cologne,Germany J.C. Dumas CEA, DES, IRESNE, DEC, L. Luzzi Politecnico di Milano, Department of Cadarache F-13108, Saint-Paul-Lez-Durance, Energy,NuclearEngineeringDivision,Milan, France Italy A. Duncan Material Sciences and Technology, A. Magni Politecnico di Milano, Department Savannah River National Laboratory, Aiken, of Energy, Nuclear Engineering Division, SC,UnitedStates Milan,Italy Tangtao Feng Department of Engineering V. Marelle CEA, DES, IRESNE, DEC, Physics, University of Wisconsin-Madison, Cadarache F-13108, Saint-Paul-Lez-Durance, Madison,WI,UnitedStates France ix x Listofcontributors R. Masson CEA, DES, IRESNE, DEC, Martin Sonnenkalb Gesellschaft fu¨r Anlagen- Cadarache F-13108, Saint-Paul-Lez-Durance, und Reaktorsicherheit (GRS) gGmbH, France Schwertnergasse,Cologne,Germany B. Michel CEA, DES, IRESNE, DEC, Claus Spengler Gesellschaft fu¨r Anlagen- und Cadarache F-13108, Saint-Paul-Lez-Durance, Reaktorsicherheit (GRS) gGmbH, France Schwertnergasse,Cologne,Germany Kaya G. Mondry Department of Engineering Guanghui Su Shaanxi Key Lab of Advanced Physics, University of Wisconsin-Madison, Nuclear Energy and Technology, School of Madison,WI,UnitedStates Nuclear Science and Technology, Xi’an Xinghe Ni College of Energy, Xiamen JiaotongUniversity,Xi’an,P.R.China University,Xiamen,P.R.China Lin Sun Department of Engineering Physics, L.Noirot CEA,DES,IRESNE,DEC,Cadarache University of Wisconsin-Madison, Madison, WI,UnitedStates F-13108,Saint-Paul-Lez-Durance,France Holger Nowack Gesellschaft fu¨r Anlagen- und Z.J. Sun Department of Health Physics and Diagnostic Science, University of Nevada Las Reaktorsicherheit (GRS) gGmbH, Schwertnergasse,Cologne,Germany Vegas,LasVegas,NV,UnitedStates Marco Pellegrini Department of Nuclear P. Van Uffelen European Commission, Joint Research Centre, Directorate for Nuclear Engineering and Management, The SafetyandSecurity,Karlsruhe,Germany UniversityofTokyo,Tokyo,Japan Alejandro Perez Department of Engineering George Vayssier Eindhoven University of Technology,Eindhoven,Netherlands Physics, University of Wisconsin-Madison, Madison,WI,UnitedStates I.Viallard CEA,DES,IRESNE,DEC,Cadarache Bowen Qiu Department of Engineering F-13108,Saint-Paul-Lez-Durance,France Physics, University of Wisconsin-Madison, Jun Wang Department of Engineering Physics, Madison,WI,UnitedStates University of Wisconsin(cid:1)Madison, Madison, I. Ramie`re CEA, DES, IRESNE, DEC, WI,UnitedStates Cadarache F-13108, Saint-Paul-Lez-Durance, Xing Wang Department of Nuclear France Engineering, Pennsylvania State University, D. Rozzia Belgian Nuclear Research Centre StateCollege,PA,UnitedStates (SCK.CEN),Mol,Belgium Zidi Wang Nuclear Safety Research Center, Shimpei Saito Graduate School of Systems JapanAtomicEnergyAgency,Ibaraki,Japan and Information Engineering, University of AndreasWielenberg Gesellschaftfu¨rAnlagen- Tsukuba,Tsukuba,Japan und Reaktorsicherheit (GRS) gGmbH, Andreas Schaffrath Gesellschaft fu¨r Anlagen- Schwertnergasse,Cologne,Germany und Reaktorsicherheit (GRS) gGmbH, Jianqi Xi Department of Materials Science and Schwertnergasse,Cologne,Germany Engineering, University of Wisconsin- A. Schubert European Commission, Joint Madison,Madison,WI,UnitedStates Research Centre, Directorate for Nuclear AkifumiYamaji CooperativeMajorinNuclear SafetyandSecurity,Karlsruhe,Germany Energy,WasedaUniversity,Tokyo,Japan J. Sercombe CEA, DES, IRESNE, DEC, JiankaiYu DepartmentofNuclearScienceand Cadarache F-13108, Saint-Paul-Lez-Durance, Engineering, Massachusetts Institute of France Technology,Cambridge,MAUnitedStates
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