Investigation of the source term in a surry TMLB{prime} sequence using VICTORIA

Journal Article · Sat Dec 30 23:00:00 EST 1995 · Transactions of the American Nuclear Society

OSTI ID:411683

Bixler, N E; Erickson, C M ^[1]; Schaperow, J H ^[2]

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1. Sandia National Lab., Albuquerque, NM (United States)
2. Nuclear Regulatory Commission, Washington, DC (United States)

The VICTORIA-92 code is a mechanistic computer code designed to analyze fission product behavior within a reactor coolant system (RCS) during a severe reactor accident. It provides detailed predictions of the release of radionuclides and nonradioactive materials from the core and transport of these materials within the RCS. These predictions account for the chemical and aerosol processes that affect radionuclide behavior. Coupling of detailed chemistry and aerosol packages is a unique feature of VICTORIA: it allows exploration of issues involving deposition, revaporization, and reentrainment that cannot be resolved with other codes.

• OSTI ID: 411683
• Report Number(s): CONF-951006--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
CORE FLOODING SYSTEMS
DESIGN BASIS ACCIDENTS
FISSION PRODUCT RELEASE
HYDRAULICS
RADIOACTIVE AEROSOLS
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
SOURCE TERMS
SURRY-1 REACTOR
V CODES