Overview of the CONTAIN LMR code

Conference · Fri Jan 01 04:00:00 EST 1988

OSTI ID:6570351

Carroll, D E

The use of containments in proposed US Liquid Metal Reactors (LMR) will require that a computational tool be available for safety analysis. As a result of an international cooperative effort, such a tool has been produced in the CONTAIN-LMR computer code. This is a version of the CONTAIN code that has been enhanced with extra capabilities for LMR applications. CONTAIN is the NRC's best-estimate code for the evaluation of the conditions that may exist inside a reactor containment building during a severe accident. Included in the phenomena modeled are thermal-hydraulics, radiant and convective heat transfer, aerosol loading and transient response, fission product transport and heating effects, and interactions of sodium and corium with the containment atmosphere and structures. CONTAIN-LMR includes models for sodium-concrete interactions, debris bed phenomena and other LMR-specific models in an integrated manner. This paper summarizes the current state of CONTAIN-LMR. A brief description of the physical models is presented. As an example of model integration in CONTAIN-LMR, recent work on the debris bed models will be discussed. Recent applications of CONTAIN-LMR are discussed. 9 refs., 5 figs.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6570351
• Report Number(s): SAND-88-2398C; CONF-8810229-2; ON: DE89004038
• Country of Publication: United States
• Language: English

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ACCIDENTS
AEROSOLS
BREEDER REACTORS
BUILDING MATERIALS
BUILDINGS
C CODES
COLLOIDS
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CONTAINMENT BUILDINGS
CORIUM
DISPERSIONS
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FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SOLS