User's manual for CONTAIN 1.1: A computer code for severe nuclear reactor accident containment analysis
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Technadyne Engineering Consultants, Inc., Albuquerque, NM (United States)
The CONTAIN 1.1 computer code is an integrated analysis tool used for predicting the physical, chemical, and radiological conditions inside a containment building following the release of radioactive environment. CONTAIN 1.1 is the US Nuclear Regulatory Commission's principal best-estimate, mechanistic containment analysis code for severe accidents. CONTAIN 1.1 is intended to replace the earlier CONTAIN 1.0, which was released in 1984. The purpose of this User's Manual is to provide a basic understanding of the features and models in CONTAIN 1.1 so that users can prepare reasonable input and understand the output and its significance for particular applications. Besides input instructions, the User's Manual also contains brief descriptions of the models. CONTAIN 1.1 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. Both light water reactors and liquid metal reactors can be modeled with CONTAIN 1.1, though many of the sodium-specific models are not documented in this report (a separate CONTAIN-LMR supplement serves this purpose). The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive heating, and the thermal-hydraulic and fission product decontamination aspects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of severe accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledgeable reactor safety analyst in evaluating the consequences of specific modeling and parameter assumptions.
- Research Organization:
- Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USNRC
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5199155
- Report Number(s):
- NUREG/CR--5026; SAND--87-2309; ON: TI90003993
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
AEROSOLS
ALGORITHMS
BREEDER REACTORS
BUILDINGS
BWR TYPE REACTORS
C CODES
CHEMICAL ANALYSIS
CHERNOBYLSK-4 REACTOR
COLLOIDS
COMPARATIVE EVALUATIONS
COMPUTER ARCHITECTURE
COMPUTER CODES
COMPUTER PROGRAM DOCUMENTATION
CONTAIN 1.1
CONTAINERS
CONTAINMENT
CONTAINMENT BUILDINGS
CONTAINMENT SYSTEMS
COOLING SYSTEMS
CORIUM
DATA BASE MANAGEMENT
DATA PROCESSING
DISPERSIONS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAILURE MODE ANALYSIS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FLUID FLOW
FLUID MECHANICS
GRAPHITE MODERATED REACTORS
HAZARDS
HEALTH HAZARDS
HEAT TRANSFER
HYDRAULICS
INFORMATION VALIDATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LWGR TYPE REACTORS
MAN-MACHINE SYSTEMS
MANAGEMENT
MATHEMATICAL LOGIC
MATHEMATICAL MODELS
MECHANICS
MELTING POINTS
PHYSICAL PROPERTIES
POWER REACTORS
PRESSURE VESSELS
PROBABILISTIC ESTIMATION
PROCESSING
PWR TYPE REACTORS
RADIATION PROTECTION
RADIOACTIVE AEROSOLS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
RISK ASSESSMENT
SAFETY
SOLS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
THERMAL REACTORS
THERMODYNAMIC PROPERTIES
THERMODYNAMICS
THREE MILE ISLAND-2 REACTOR
TRANSITION TEMPERATURE
V CODES
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
aerosol behavior
computer code
fission products
reactor containment
severe accidents
thermal-hydraulic behavior