Reference manual for the CONTAIN 1. 1 code for containment severe accident analysis
- Sandia National Labs., Albuquerque, NM (USA)
- Los Alamos Technical Associates, Inc., Albuquerque, NM (USA)
This report describes the phenomenological equations and the numerical procedures used by the CONTAIN 1.1 code to determine the conditions within nuclear power plant containment during a severe accident. The CONTAIN detailed models provide the capability to mechanistically calculate the containment internal thermalhydraulic conditions and the amount of radioactive matter that would be released to the environment if there were a leak from the containment. Note that the CONTAIN models can be verified by comparing the code calculations to experimental results. The models described include those to account for the flows of mass and energy between containment compartments, the exchange of energy between the atmosphere and heat structures, the thermodynamic conditions, the distributions of aerosols, the decay and transport of fission products, the deflagration of hydrogen and carbon monoxide, boiling water reactor suppression pool behavior, and engineering safety features, including a spray, fan coolers, and an ice condenser. These models are solved with implicit coupling, where appropriate, to obtain a stable and computationally efficient solution. 52 refs., 36 figs., 9 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5374267
- Report Number(s):
- NUREG/CR-5715; SAND-91-0835; ON: TI91016470
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
C CODES
CONTAINMENT
NUCLEAR POWER PLANTS
CONTAINMENT SYSTEMS
AEROSOLS
CARBON MONOXIDE
COMBUSTION
CONCRETES
CORIUM
ENGINEERED SAFETY SYSTEMS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
HEAT TRANSFER
HYDRAULICS
HYDROGEN
ICE CONDENSERS
RADIOACTIVE EFFLUENTS
THERMODYNAMICS
BUILDING MATERIALS
CARBON COMPOUNDS
CARBON OXIDES
CHALCOGENIDES
CHEMICAL REACTIONS
COLLOIDS
COMPUTER CODES
CONDENSERS
DISPERSIONS
ELEMENTS
ENERGY TRANSFER
FLUID MECHANICS
ISOTOPES
MATERIALS
MECHANICS
NONMETALS
NUCLEAR FACILITIES
OXIDATION
OXIDES
OXYGEN COMPOUNDS
POWER PLANTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SOLS
STEAM CONDENSERS
THERMAL POWER PLANTS
THERMOCHEMICAL PROCESSES
VAPOR CONDENSERS
WASTES
220502* - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents
990200 - Mathematics & Computers
220900 - Nuclear Reactor Technology- Reactor Safety