SCDAP/RELAP5/MOD3 code development

Conference · Thu Dec 31 04:00:00 EST 1992

OSTI ID:10115932

Allison, C M; Siefken, J L; Coryell, E W

The SCOAP/RELAP5/MOD3 computer code is designed to describe the overall reactor coolant system (RCS) thermal-hydraulic response, core damage progression, and fission product release and transport during severe accidents. The code is being developed at the Idaho National Engineering Laboratory (INEL) under the primary sponsorship of the Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission (NRC). Code development activities are currently focused on three main areas - (a) code usability, (b) early phase melt progression model improvements, and (c) advanced reactor thermal-hydraulic model extensions. This paper describes the first two activities. A companion paper describes the advanced reactor model improvements being performed under RELAP5/MOD3 funding.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 10115932
• Report Number(s): EGG-M--92630; CONF-921007--14; ON: DE93005183
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200
220504
220900
99 GENERAL AND MISCELLANEOUS
990200
COMPONENTS AND ACCESSORIES
DESIGN
DESIGN BASIS AND HYPOTHETICAL ACCIDENTS
FISSION PRODUCT RELEASE
HEAT TRANSFER
HYDRAULICS
MATHEMATICS AND COMPUTERS
MODIFICATIONS
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
S CODES