SCDAP/RELAP5/MOD3 code development
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:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6912357
- Report Number(s):
- EGG-M-92630; CONF-921007--14; ON: DE93005183
- Country of Publication:
- United States
- Language:
- English
Similar Records
The SCDAP/RELAP5 development and assessment highlights
SCDAP/RELAP5 code development and assessment
Related Subjects
220200 -- Nuclear Reactor Technology-- Components & Accessories
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
DESIGN
ENERGY TRANSFER
FISSION PRODUCT RELEASE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
MODIFICATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
S CODES