Status of VICTORIA: NRC peer review and recent code applications
- Sandia National Labs., Albuquerque, NM (United States)
- Nuclear Regulatory Commission, Washington, DC (United States)
VICTORIA is a mechanistic computer code designed to analyze fission product behavior within a nuclear reactor coolant system (RCS) during a severe accident. It provides detailed predictions of the release of radioactive and nonradioactive materials from the reactor core and transport and deposition of these materials within the RCS. A summary of the results and recommendations of an independent peer review of VICTORIA by the US Nuclear Regulatory Commission (NRC) is presented, along with recent applications of the code. The latter include analyses of a temperature-induced steam generator tube rupture sequence and post-test analyses of the Phebus FPT-1 test. The next planned Phebus test, FTP-4, will focus on fission product releases from a rubble bed, especially those of the less-volatile elements, and on the speciation of the released elements. Pretest analyses using VICTORIA to estimate the magnitude and timing of releases are presented. The predicted release of uranium is a matter of particular importance because of concern about filter plugging during the test.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE Assistant Secretary for Human Resources and Administration, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 563203
- Report Number(s):
- SAND-97-3106C; CONF-9710101-; ON: DE98001677; BR: 401001060; TRN: 98:002643
- Resource Relation:
- Conference: 25. water reactor safety information meeting, Bethesda, MD (United States), 20-22 Oct 1997; Other Information: PBD: [1997]
- Country of Publication:
- United States
- Language:
- English
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