AP600 large-break loss-of-collant-accident developmental assessment plan for TRAC-PF1/MOD2
The Westinghouse AP600 reactor is an advanced pressurized water reactor with passive safety systems to protect the plant against possible accidents and transients. The design has been submitted to the U.S. NRC for design certification. The NRC has selected the Transient Reactor Analysis Code (TRAC)-PF1/MOD2 for performing large break loss-of coolant-accident (LBLOCA) analysis to support the certification effort. This document defines the tests to be used in the current phase of developmental assessment related to AP600 LBLOCA.
- Research Organization:
- Los Alamos National Lab., NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 366497
- Report Number(s):
- LA-UR--96-2700; ON: DE96014433
- Country of Publication:
- United States
- Language:
- English
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