Liquid metal reactor applications of the CONTAIN code
Conference
·
OSTI ID:5262139
The CONTAIN code is the NRC's best-estimate code fo the evaluation of the conditions that may exist inside a reactor containment building during a severe accident. Included in the phenomena modeled are thermal-hydrulics, 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 has been used by groups in Japan and West Germany to assess its ability to analyze accident consequences for Liquid Metal Reactor (LMR) plants. In conjuction with this use, collaborative efforts to improve the modeling capabilities of CONTAIN for LMR applications have been pursued. This paper summarizes the current state of the version of CONTAIN that has been enhanced with extra capabilities for LMR applications. A brief description of physical models is presented, followed by a short review of validation exercises performed with CONTAIN. Finally, some demonstration calculations of an integrated LMR application are presented. 11 refs., 5 figs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA); Los Alamos National Lab., NM (USA); Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA); Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5262139
- Report Number(s):
- SAND-88-0837C; CONF-880532-8; ON: DE88008108
- Country of Publication:
- United States
- Language:
- English
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C CODES
COLLOIDS
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COMPUTER CODES
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
DISPERSIONS
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
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REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SODIUM
SOLS
TRANSIENTS
WASTES