Compare containment subcompartment analysis code evaluation
Description
Nuclear power plant subcompartment analyses are required to determine the containment pressure distribution that might result from a loss-of-coolant accident. The pressure distribution is used to calculate structural and mechanical design loads. The COMPARE code is used widely to perform subcompartment analysis. However, several simplifying assumptions are utilized to facilitate solution of the complex transient, two-phase, multidimensional flow problem. In particular, it is assumed that the flow is homogeneous, in thermodynamic equilibrium, and one-dimensional. In this study, these assumptions are evaluated by performing simplified transport and relaxation analyses. This results in definition of (a) geometric features and early-time periods that produce significant deviations from reality and (b) specific areas that require further study
Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Title
- Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 3
- Journal Page Range
- p. 1583-1596.
- Report number
- NUREG/CP--0027-Vol.3
Conference
- Title
- International meeting on thermal nuclear reactor safety (ANS topical meeting).
- Dates
- 29 Aug - 2 Sep 1982.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14792466
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CALCULATIONS; CONTAINMENT BUILDINGS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS