Development of Thermal-hydraulic Nuclear Safety Analysis Code in Japan and Overseas Countries m BWR TMI JAEA USNRC ROSA LSTF THYNC

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1 Development of Thermal-hydraulic Nuclear Safety Analysis Code in Japan and Overseas Countries m BWR TMI JAEA USNRC ROSALSTFTHYNC

2 EMBWR BWR LAMBSCATSAFERCHASTE PWRSATAN-MWREFLOODBASH- MCOCOLOCTA-MLOCTA-IV BETMI BEBWR EM EMBWR BEBWR

3 BEPU best estimate plus uncertainty BEPU CFD BE CFD PWRcmm cmm cm m EM EM BEPUBE

4 BECFD BE BECFD BEPU V&V BEPU CFDBest Practice Guideline CFD V&V User Effect OECD/NEA Reference DataUser Effect BE V&V

5 OECD/NEA ISP JAEAOECD ROSA BE WREMEM EM EM THYDE-BTHYDE-P EM BE RELAP RELAP TRAC USNRC TRACRELAP TRACE BE EMBE BE USNRC up-to-datebe BE USNRCRELAP RELAPTRACTRACECEA EdFAREVA_NPIRSNCATHARE GRSATHLET VTTFortumAprosNRG SPECTRA KAERI MARS SPACESNPSDCCOSINE BE LOCA/ECCS TMILOCA EM BE BE BE

6 MWeWestinghousePWR CANDU ABB Combustion EngineeringCESystem-kW OPR System-+ kw APR RCP MMIS APR USNRC MESTMOST MKE NuTech- KAERIKEPCO KEPRI KHNPNETEC ' iwestinghouse WHABB-CEAECL EM iibe iiiusnrcrelap RELAP/Mod/K * KEPRI Realistic Evaluation Model KREM LOCA BEUSNRCRELAP Mod Mod Mod COBRA- TFTRACTRACESNAPCEA CATHAREAECL CATHENA USNRC ICAPCAMPUSNRC i ii USNRCRELAP COBRA-TF BEMARS iiiiem i *1 KUSNRCAppendix K

7 LOCA LOCA WH-CENP (ABB-CE) LTC CESEC STRIKIN-II TORC /CETOP CEFLASH-4AS CEFLASH-4A /COMPERC-II CEFLASH-4B CONTEMPT-LT WH LOFTRAN LOFTRAN PAD /LOC /BART THINC /BANDIT NOTRUMP SATAN6 /BASH MUTLIFLEX CONTEMPT-LT RETRAN-3D/M D RETRANMASTER TORC TORC DNB LOCA RELAP5+Appendix K LOCAiii KREM BE PWRCANDU Gen-IV BE RELAP COBRA-TFMARS MARS PWR CANDU SMARTGen-IV MARS KAERI OPR APR MESTMOST Fortran DLL

8 CONTAIN CONTEMPT MASTER MIDAS RELAP/Mod OECD/NEA KAERIOECD/NEA SETHPKL PANDA PKLBFBTUSNRC ROSAJAEA LSTFBEMUSELOFT LOCAZionBEPU SMA MARS Users GroupMUG MUG RELAP MUG USNRCCAMP GUI RETRANPWR ViSA MARS MEST KINS KINS-RETAS MARS

9 MARS-KSKAERI MUG CFD MARS APRBE SPACE MARSKAERI MARS SPACE MEST MKEKHNP MARS V&V KINS SPACE KAERIKOPEC KNFCKHNP SPACE SPACEMARS C Lumped Model KAERIRELAP TRACECATHARE V&V PIRT APR/ ATLAS SPACE MARS KAERI KAERI KAERI KAERI

10 MARSSPACE CUPID SPACE CUPID KINSRETAS SPACE SNERDI kwe ' PWRCANDU VVERAP PWR CNNC CGNPC SNPTC PWR CNNCCPR Westinghouse AP USNRC Westinghouse kw SNPTCkW kwcap CAP CNNCSNERDISNPTC SNPSDC SNPTC AP CAP COSINE Core and System Integrated Engine for design and analysis

11 BE SPACE V&V COSINE SPACE Lumped Model PWR BE Fortran V&V USNRC ISO- CMMI Capability Maturity Model Integration QEPQuality Enhancement ProgramUSNRC RG BE RG EMDAP V&V a OSUAPEX * b c d e f IVR JAEA LSTFOECD ROSA *AP/// HLCL

12 V&V GUI V&V V&V V&V V&V BE IAEA ATOMICA ATOMICA ATOMICA ( ) JAEA :2008AESJ-SC-S001:2008 :ASME, Standard for Verification and Validation in Computational Fluid Dynamics and Heat Transfer, ASME V&V :OECD/NEA, BEMUSE Phase VI Report - Status report on the area, classification of the methods, conclusions and recommendations, NEA/CSNI/R (2011) 4 OECD/NEA, Best Practice Guidelines

13 for the use of CFD in Nuclear Reactor Safety Applications,NEA/ CSNI/R (2007) 5 OECD/NEA, Assessment of CFD for Nuclear Reactor Safety Problems, NEA/CSNI/R(2007)13 OECD/NEA, Extension of CFD Codes Application to Two-Phase Flow Safety Problems - Phase 2, NEA/CSNI/R(2010)2 OECD/NEA (JAEAROSA-2) ( : OECD/NEA, International Standard Problem ISP - 47 on Containment Thermal Hydraulics: Final Report,NEA/CSNI/R (2007) IX Ohmsha W.-P. Baek, J.-E. Yang and J.-J. Ha, Safety Assessment of Korean Nuclear Facilities: Current Status and Future, Nucl. Engng. and Technol., vol.41 no.4 (2009) pp 391. KAERI MARS ( 1:J. Kim, K. Kim and K. Seul, Simulation of SBLOCA in RD-14M Test Facility using Computer Code MARS_KS, Proc. NUTHOS - 8, N8P0329, Shanghai (2010) 2:Y.S. Bang, J.H. Chun, S.S. Jeon, G.C. Park, MARS Code Improvements for Condensation Heat Transfer in Vertical Tube with Presence of Non-Condensable Gas,Proc. NURETH-13, N13P1270, Kanazawa (2009) D.-H. Lee, C.-K. Yang, S. Kim, S.-J. Ha. Overview of SPACE Thermalhydraulic Analysis Code Development, Proc. NUTHOS-7, Seoul (2008) K.D. Kim, S.W. Lee, S.W. Bae, S.K. Moon, S.H. Kim, Development of Physical Models and Correlation Packages for the SPACE code,proc. NURETH-13, N13P1321, Kanazawa (2009) :B.J. Kim, M.K. Hwang, K.D. Kim and S.W. Lee, Assessment of the Wall and Interphase Friction Modules in SPACE Code, Proc. NUTHOS-8, N8P0260, Shanghai (2010) J.J. Jeong, H.Y. Yoon, I.K. Park and H. K. Cho, The CUPID Code Development and Assessment Strategy,Nucl. Engng. and Technol., vol.42 no.6 (2010) pp 637. Software Engineering Institute, CMMI for Development, Version 1.2, CMU/SEI-2006-TR-008, ESC- TR (2006) NRC Regulatory Guide, 1.157: Best- Estimate Calculations of Emergency Core Cooling System Performance, (1989) NRC Regulatory Guide, 1.203: Transient and Accident Analysis Methods,(2005) USNRC,APEX-AP1000 Confirmatory Testing to Support AP1000 Design Certification (Non - Proprietary), NUREG-1826 (2005). eye, vol.57, No.6 (2011) 29

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