OVERVIEW OF RECENT EFFORTS THROUGH ROSA/LSTF EXPERIMENTS

HIDEO NAKAMURA; TADASHI WATANABE; TAKESHI TAKEDA; YU MARUYAMA; MITSUHIRO SUZUKI

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자료유형: 학술저널

저자정보: HIDEO NAKAMURA TADASHI WATANABE TAKESHI TAKEDA YU MARUYAMA MITSUHIRO SUZUKI

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제41권 제6호

발행연도: 2009.1

수록면: 753 - 764 (12page)

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JAEA started the LSTF experiments in 1985 for the fourth stage of the ROSA Program (ROSA-IV) for the LWR thermal-hydraulic safety research to identify and investigate the thermal-hydraulic phenomena and to confirm the effectiveness of ECCS during small-break LOCAs and operational transients. The LSTF experiments are underway for the ROSA-V Program and the OECD/NEA ROSA Project that intends to resolve issues in thermal-hydraulic analyses relevant to LWR safety. Six types of the LSTF experiments have been done for both the system integral and separate-effect experiments among international members from 14 countries. Results of four experiments for the ROSA Project are briefly presented with analysis by a best-estimate (BE) code and a computational fluid dynamics (CFD) code to illustrate the capability of the LSTF and codes to simulate the thermal-hydraulic phenomena that may appear during SBLOCAs and transients. The thermal-hydraulic phenomena dealt with are coolant mixing and temperature stratification, water hammer up to high system pressure, natural circulation under high core power condition, and non-condensable gas effect during asymmetric SG depressurization as an AM action.

#LSTF #ROSA Program #Integral-effect and Separate-effect Tests #Thermal-hydraulics #OECD/NEA ROSA Project

참고문헌 (24)

참고문헌 신청

/ 2005 / FLUENT 6.2 User’s Guide, Fluent Inc. (2005)

F. Serre / 1990 / CATHARE Analysis of Natural Circulation under Normal and Degraded Secondary Cooling Conditions in LSTF Runs ST-NC-06 and ST-NC-07 / EUROTHERM Seminar No. 16, Nat

H. Adachi / 1982 / ROSA-II experimental program for PWR LOCA/ECCS integral tests

H. Kumamaru / 1992 / Pressurized Water Reactor Small Break LOCA: Effect of Break Area and Intentional System Depressurization for Prevention of Excess Core Dryout / J. Nucl.

H. Nakamura / 1994 / PWR thermal-hydraulic phenomena following loss of residual heat removal (RHR) during mid-loop operation / Proc. of Int. Conf. on New Trends in Nucl. System Th

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