ROSA/LSTF test and RELAP5 code analyses on PWR 1% vessel upper head small-break LOCA with accident management measure based on core exit temperature

Author:

Takeda Takeshi

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference28 articles.

1. Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, Bulletin 2002-01, OMB Control No.: 3150-0012;USNRC,2002

2. Overview of recent efforts through ROSA/LSTF experiments;Nakamura;Nucl. Eng. Technol.,2009

3. Large Scale Test Facility (LSTF) System Description for the Third and Fourth Simulated Fuel Assemblies, JAERI-tech 2003-037;The ROSA-V Group,2003

4. The effects of break locaion on PWR small break LOCA: experimental study at the ROSA-IV LSTF;Kukita;Nucl. Eng. Des.,1990

5. Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE;Freixa;Nucl. Eng. Des.,2010

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