SCDAP/RELAP5/MOD3 code development

Conference · Thu Dec 31 00:00:00 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
• Resource Relation: Conference: 20. water reactor safety information meeting,Bethesda, MD (United States),21-23 Oct 1992; Other Information: PBD: [1992]
• Country of Publication: United States
• Language: English

Related Subjects

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