SPERT benchmarks of the HFIR dynamic model
Creators
- 1. Univ. of Tennessee, Knoxville (United States)
- 2. Oak Ridge National Lab., TN (United States)
Description
After the shutdown of Oak Ridge National Laboratory's high-flux isotope reactor (HFIR) in November 1986 because of embrittlement concerns, some of the design parameters were changed to ensure safe operation of the reactor with the existing pressure vessel. To properly document these changes and their effects on reactor operation, the safety analysis report of the HFIR is currently being updated. As part of this effort, an improved dynamic model of the HFIR core was developed, and the response of the HFIR to reactivity-induced accidents was analyzed. When compared to previous analog computer calculations, good agreement was achieved between the calculated and analog results except for low-power, low-flow transients. To further investigate low-power, low-flow transients, the short-period excursion reactor transients (SPERT) experiments have been calculated using the improved HFIR dynamic model. The purpose of this paper is to present the results of these comparisons
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 250-251
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Annual meeting of the American Nuclear Society (ANS).
- Dates
- 2-6 Jun 1991.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23036877
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; EMBRITTLEMENT; EXPERIMENTAL DATA; FLOW RATE; HEAT TRANSFER; HFIR REACTOR; HYDRAULICS; MULTIPLICATION FACTORS; ORNL; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; REACTIVITY; REACTOR KINETICS; REACTOR OPERATION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; TRANSIENTS; US DOE
- Descriptors DEC
- CONTAINERS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; INFORMATION; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; KINETICS; NATIONAL ORGANIZATIONS; NUMERICAL DATA; OPERATION; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SIMULATION; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; US AEC; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-910603--.