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TRACE/PARCS analysis of the OECD/NEA Oskarshamn-2 BWR stability benchmark

Conference ·
OSTI ID:22105716
 [1]; ; ;  [2]; ; ;  [3];  [4]; ;  [5]
  1. Univ. of Illinois, Urbana-Champaign, IL (United States)
  2. Univ. of Michigan, Ann Arbor, MI (United States)
  3. Pennsylvania State Univ., Univ. Park, PA (United States)
  4. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
  5. Nuclear Regulatory Commission, Rockville, MD (United States)
+ Show Author Affiliations
On February 25, 1999, the Oskarshamn-2 NPP experienced a stability event which culminated in diverging power oscillations with a decay ratio of about 1.4. The event was successfully modeled by the TRACE/PARCS coupled code system, and further analysis of the event is described in this paper. The results show very good agreement with the plant data, capturing the entire behavior of the transient including the onset of instability, growth of the oscillations (decay ratio) and oscillation frequency. This provides confidence in the prediction of other parameters which are not available from the plant records. The event provides coupled code validation for a challenging BWR stability event, which involves the accurate simulation of neutron kinetics (NK), thermal-hydraulics (TH), and TH/NK. coupling. The success of this work has demonstrated the ability of the 3-D coupled systems code TRACE/PARCS to capture the complex behavior of BWR stability events. The problem was released as an international OECD/NEA benchmark, and it is the first benchmark based on measured plant data for a stability event with a DR greater than one. Interested participants are invited to contact authors for more information. (authors)
Research Organization:
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
OSTI ID:
22105716
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BENCHMARKS
COMPUTER CODES
COMPUTERIZED SIMULATION
DECAY
KINETICS
NEUTRONS
OKG-2 REACTOR
OSCILLATIONS
REACTOR STABILITY
THERMAL HYDRAULICS
THREE-DIMENSIONAL CALCULATIONS
VALIDATION