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Investigation of a steam generator tube rupture sequence using VICTORIA [electronic resource].

Published
Rockville, Md. : U.S. Nuclear Regulatory Commission, 1995.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
20 pages : digital, PDF file
Additional Creators
Sandia National Laboratories, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
VICTORIA-92 is a mechanistic computer code for analyzing fission product behavior within the 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. The modeling accounts 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 phenomena involving deposition, revaporization, and re-entrainment that cannot be resolved with other codes. The purpose of this work is to determine the attenuation of fission products in the RCS and on the secondary side of the steam generator in an accident initiated by a steam generator tube rupture (SGTR). As a class, bypass sequences have been identified in NUREG-1150 as being risk dominant for the Surry and Sequoyah pressurized water reactor (PWR) plants.
Report Numbers
E 1.99:sand--95-2973c
E 1.99: conf-9510156--4
conf-9510156--4
sand--95-2973c
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
12/31/1995.
"sand--95-2973c"
" conf-9510156--4"
"DE96003699"
23. water reactor safety information meeting, Bethesda, MD (United States), 23-25 Oct 1995.
Erickson, C.M.; Bixler, N.E.; Schaperow, J.H.
Funding Information
AC04-94AL85000
View MARC record | catkey: 14365588