Extension of SCDAP/RELAP5 severe accident models to non-LWR reactor designs. [Non-Light Water Reactors]

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6491536

Allison, C M; Siefken, L J; Hagrman, D L ^[1]; Cheng, T C ^[2]

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1. EG and G Idaho, Inc., Idaho Falls, ID (USA)
2. Los Alamos National Lab., NM (USA)

The SCDAP/RELAP5 code has been extended to calculate the core melt progression and fission product transport that may occur in non-LWR reactors during severe accidents. The code's approach of connecting together according to user instructions all of the parts that constitute a reactor system give the code the capability to model a wide range of reactor designs. The models added to the code for analyses of non-LWR reactors include: (a) oxidation and melt progression in cores with U-Al based fuel elements, (b) movement of liquefied material from its original place in the core to other parts of the reactor systems, such as the outlet piping, (c) fission product release from U-Al based fuel and zinc release from aluminum, and (d) fission product release from a pool of molten core material. 9 refs., 5 figs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6491536
• Report Number(s): EGG-M-89534; CONF-900917-19; ON: DE91001830; TRN: 90-035953
• Resource Relation: Conference: American Nuclear Society topical meeting on safety of non-commercial nuclear reactor research and irradiation facilities, Boise, ID (USA), 30 Sep - 3 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
AEROSOLS
RADIOACTIVITY TRANSPORT
CORIUM
FLOW MODELS
FISSION PRODUCTS
FISSION PRODUCT RELEASE
FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
MELTDOWN
R CODES
REACTOR SAFETY
S CODES
TEMPERATURE DISTRIBUTION
ACCIDENTS
COLLOIDS
COMPUTER CODES
DISPERSIONS
ENERGY TRANSFER
ISOTOPES
MATERIALS
MATHEMATICAL MODELS
MECHANICS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
SAFETY
SOLS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
990200 - Mathematics & Computers