TRAC analysis of the system pressure effects tests in the Slab Core Test Facility
Description
This paper describes the analysis, using the TRAC computer code, of three system pressure effects reflood tests performed during 1981 at the Slab Core Test Facility at the Japan Atomic Energy Research Institute in Tokai, Japan. Comparisons of the calculated results with the experimental data were very good, particularly for rod temperature histories, core differential pressures, mass inventories, liquid carryover, and fluid velocities in the loops. These comparisons indicate that the TRAC code can predict reasonably well the effects of pressure variations in test conditions. This and similar calculations demonstrate that TRAC is a useful tool for the design of nuclear reactor systems and the analysis of system response during postulated accident sequences
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Title
- Proceedings on the international meeting on thermal nuclear reactor safety. Vol. 3
- Journal Page Range
- p. 1923-1930.
- 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
- 14792490
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS