Thermal hydraulic-severe accident code interfaces for SCDAP/RELAP5/MOD3.2

Conference · Tue Jul 01 00:00:00 EDT 1997

OSTI ID:544395

Coryell, E W; Siefken, L J; Harvego, E A ^[1]

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1. Idaho National Engineering Lab., Idaho Falls, ID (United States); and others

The SCDAP/RELAP5 computer code is designed to describe the overall reactor coolant system thermal-hydraulic response, core damage progression, and fission product release during severe accidents. The code is being developed at the Idaho National Engineering Laboratory under the primary sponsorship of the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The code is the result of merging the RELAP5, SCDAP, and COUPLE codes. The RELAP5 portion of the code calculates the overall reactor coolant system, thermal-hydraulics, and associated reactor system responses. The SCDAP portion of the code describes the response of the core and associated vessel structures. The COUPLE portion of the code describes response of lower plenum structures and debris and the failure of the lower head. The code uses a modular approach with the overall structure, input/output processing, and data structures following the pattern established for RELAP5. The code uses a building block approach to allow the code user to easily represent a wide variety of systems and conditions through a powerful input processor. The user can represent a wide variety of experiments or reactor designs by selecting fuel rods and other assembly structures from a range of representative core component models, and arrange them in a variety of patterns within the thermalhydraulic network. The COUPLE portion of the code uses two-dimensional representations of the lower plenum structures and debris beds. The flow of information between the different portions of the code occurs at each system level time step advancement. The RELAP5 portion of the code describes the fluid transport around the system. These fluid conditions are used as thermal and mass transport boundary conditions for the SCDAP and COUPLE structures and debris beds.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Systems Technology; Nuclear Energy Agency, 75 - Paris (France); SCIENTECH, Inc., Boise, ID (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 544395
• Report Number(s): NUREG/CP-0159; NEA/CSNI/R-(97)4; CONF-961192-; ON: TI97008508; TRN: 98:000233
• Resource Relation: Conference: Organization for Economic Co-Operation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) workshop on transient thermal-hydraulic codes requirements, Annapolis, MD (United States), 5-8 Nov 1996; Other Information: PBD: Jul 1997; Related Information: Is Part Of Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements; Ebert, D.; PB: 824 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
REACTOR ACCIDENTS
COMPUTERIZED SIMULATION
COMPUTER CODES
MODIFICATIONS
USES
S CODES
C CODES
HYDRAULICS
TRANSIENTS
REACTOR CORE DISRUPTION
FISSION PRODUCT RELEASE