CONTAIN LMR/1B-Mod.1, A computer code for containment analysis of accidents in liquid-metal-cooled nuclear reactors
- Sandia National Labs., Albuquerque, NM (United States)
- Applied Methods, Inc., Albuquerque, NM (United States)
The CONTAIN computer code is a best-estimate, integrated analysis tool for predicting the physical, chemical, and radiological conditions inside a nuclear reactor containment building following the release of core material from the primary system. CONTAIN is supported primarily by the U. S. Nuclear Regulatory Commission (USNRC), and the official code versions produced with this support are intended primarily for the analysis of light water reactors (LWR). The present manual describes CONTAIN LMR/1B-Mod. 1, a code version designed for the analysis of reactors with liquid metal coolant. It is a variant of the official CONTAIN 1.11 LWR code version. Some of the features of CONTAIN-LMR for treating the behavior of liquid metal coolant are in fact present in the LWR code versions but are discussed here rather than in the User`s Manual for the LWR versions. These features include models for sodium pool and spray fires. In addition to these models, new or substantially improved models have been installed in CONTAIN-LMR. The latter include models for treating two condensables (sodium and water) simultaneously, sodium atmosphere and pool chemistry, sodium condensation on aerosols, heat transfer from core-debris beds and to sodium pools, and sodium-concrete interactions. A detailed description of each of the above models is given, along with the code input requirements.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States); Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 10122588
- Report Number(s):
- SAND--91-1490; ON: DE93007424
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210500
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
C CODES
CHEMICAL REACTION KINETICS
CONTAINMENT
CORIUM
FIRES
HEAT TRANSFER
HYDRAULICS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MATHEMATICS AND COMPUTERS
POWER REACTORS
BREEDING
REACTOR ACCIDENTS
REACTOR SAFETY
SODIUM