CONTAIN independent peer review
Creators
- 1. Los Alamos National Lab., NM (United States)
- 2. Univ. of Wisconsin, Madison, WI (United States). Nuclear Engineering Dept.
- 3. Battelle Memorial Inst., Columbus, OH (United States)
- 4. Energy Research Inc., Rockville, MD (United States)
- 5. Univ. of Missouri, Columbia, MO (United States)
- 6. AEA Technology, Dorchester (United Kingdom). Winfrith Technology Center
Description
The CONTAIN code was developed by Sandia National Laboratories under the sponsorship of the US Nuclear Regulatory Commission (NRC) to provide integrated analyses of containment phenomena. It is used to predict nuclear reactor containment loads, radiological source terms, and associated physical phenomena for a range of accident conditions encompassing both design-basis and severe accidents. The code's targeted applications include support for containment-related experimental programs, light water and advanced light water reactor plant analysis, and analytical support for resolution of specific technical issues such as direct containment heating. The NRC decided that a broad technical review of the code should be performed by technical experts to determine its overall technical adequacy. For this purpose, a six-member CONTAIN Peer Review Committee was organized and a peer review as conducted. While the review was in progress, the NRC issued a draft ''Revised Severe Accident Code Strategy'' that incorporated revised design objectives and targeted applications for the CONTAIN code. The committee continued its effort to develop findings relative to the original NRC statement of design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications were considered by the Committee in assigning priorities to the Committee's recommendations. The Committee determined some improvements are warranted and provided recommendations in five code-related areas: (1) documentation, (2) user guidance, (3) modeling capability, (4) code assessment, and (5) technical assessment
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE95006356; NTIS; US Govt. Printing Office Dep.Files
26041560.pdf
Files
(46.2 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 306 p.
- Report number
- LA--12866
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26041560
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- C CODES; CHEMICAL REACTIONS; COMBUSTION; CONTAINMENT SYSTEMS; CORIUM; EVALUATION; FISSION PRODUCT RELEASE; HEAT TRANSFER; MODIFICATIONS; PRESSURE VESSELS; RADIOACTIVE AEROSOLS; REACTOR ACCIDENTS; RECOMMENDATIONS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; AEROSOLS; COLLOIDS; COMPUTER CODES; CONTAINERS; CONTAINMENT; DISPERSIONS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; OXIDATION; REACTORS; SOLS
Optional Information
- Contract/Grant/Project number
- Contract W-7405-ENG-36
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).