SPERT benchmarks of the HFIR dynamic model

Conference · Tue Jan 01 04:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5776617

Sofu, T; Ibn-Khayat, M; Dodds, H L ^[1]; Cook, D H ^[2]

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1. Univ. of Tennessee, Knoxville (United States)
2. Oak Ridge National Lab., TN (United States)

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.

• OSTI ID: 5776617
• Report Number(s): CONF-910603--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
DATA
EMBRITTLEMENT
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HFIR REACTOR
HYDRAULICS
INFORMATION
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
KINETICS
MECHANICS
MULTIPLICATION FACTORS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
OPERATION
ORNL
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTIVITY
REACTOR KINETICS
REACTOR OPERATION
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
TRANSIENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS