Universal treatment of plumes and stresses for pressurized thermal shock evaluations
Creators
- 1. Univ. of California, Santa Barbara (United States)
Description
Thermally-induced stresses in a reactor pressure vessel wall, as a result of high-pressure safety injection, are an essential component of integrated risk analyses of pressurized thermal shock transients. Limiting cooldowns arise when this injection occurs under stagnated loop conditions which, in turn, correspond to a rather narrow range (in size) of small-break loss-of-coolant accidents. Moreover, at these conditions, the flow is thermally stratified, and in addition to the global cooldown, one must be concerned about the additional cooling potential due to the downcomer plumes formed by the cold streams pouring out of the cold legs. In the Nuclear Regulatory Commission's Integrated Pressurized Thermal Shock (IPTS) study, this stratification was calculated with the codes REMIX/NEWMIX. A comprehensive comparison with all available experimental data has currently been compiled. The stress analysis using this input was carried out at Oak Ridge National Laboratory using a one-dimensional approximation with the intent to conservatively bound the magnitude of thermal stresses
Files
Additional details
Publishing Information
- Imprint Title
- Transactions of the nineteenth water reactor safety information meeting
- Imprint Pagination
- 220 p.
- Journal Page Range
- p. 18.15-18.16.
- Report number
- NUREG/CP--0118
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059499
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CALVERT CLIFFS-1 REACTOR; COMPUTER CODES; COMPUTERIZED SIMULATION; HIGH PRESSURE COOLANT INJECTIO; LOSS OF COOLANT; MATHEMATICAL MODELS; N CODES; ONE-DIMENSIONAL CALCULATIONS; ORNL; PRESSURE VESSELS; PRESSURIZATION; PWR TYPE REACTORS; R CODES; REACTOR SAFETY; STRATIFICATION; THERMAL SHOCK; THERMAL STRESSES; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ECCS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; STRESSES; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--.