Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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OVERVIEW OF RECENT EFFORTS THROUGH ROSA/LSTF EXPERIMENTS

  • Nakamura, Hideo (Japan Atomic Energy Agency (JAEA), Nuclear Safety Research Center, Thermohydraulic Safety Research Group) ;
  • Watanabe, Tadashi (Japan Atomic Energy Agency (JAEA), Nuclear Safety Research Center, Thermohydraulic Safety Research Group) ;
  • Takeda, Takeshi (Japan Atomic Energy Agency (JAEA), Nuclear Safety Research Center, Thermohydraulic Safety Research Group) ;
  • Maruyama, Yu (Japan Atomic Energy Agency (JAEA), Nuclear Safety Research Center, Thermohydraulic Safety Research Group) ;
  • Suzuki, Mitsuhiro (Japan Atomic Energy Agency (JAEA), Nuclear Safety Research Center, Thermohydraulic Safety Research Group)
  • Published : 2009.08.31
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Abstract

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.

Keywords

References

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