Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

VICTORIA sensitivity studies of induced steam generator tube rupture

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:552621
 [1];  [2]
  1. Sandia National Labs., Albuquerque, NM (United States)
  2. Nuclear Regulatory Commission, Washington, DC (United States)

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

OSTI ID:
552621
Report Number(s):
CONF-971125--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; ISSN 0003-018X; ISSN TANSAO
Country of Publication:
United States
Language:
English