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Findings of an International Study on Burnup Credit

Conference ·
OSTI ID:273652
 [1];  [2];  [2];  [3];  [4];  [5]
  1. Sandia National Laboratories (SNL), Las Vegas, NV (United States)
  2. Japan Atomic Energy Research Institute (JAERI), Tokai (Japan)
  3. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  4. IPSN/DPEA/SEC, Fontenay-aux-Roses, (France). Inst. de Protection et de Surete Nucleaire
  5. Organisation for Economic Co-operation and Development (OECD), Paris (France). Nuclear Energy Agency (NEA)
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Findings from a four-year study by an international benchmarking group in the comparison of computational methods for evaluating burnup credit in criticality safety analyses are presented in this paper. Approximately 20 participants from 11 countries have provided results for most problems. Four detailed benchmark problems for Pressurized Water Reactor (PWR) fuel have been completed and are summarized in this paper. Preliminary results from current work addressing burnup credit for Boiling Water Reactor (BWR) fuel will also be discussed as well as planned activities for additional benchmarks including Mixed-Oxide (MOX) fuels, subcritical benchmarks, international databases, and other activities.

Research Organization:
Sandia National Laboratories (SNL), Las Vegas, NV (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AC04-94AL85000
OSTI ID:
273652
Report Number(s):
SAND--96-2056C; CONF-960924--5; ON: DE96014077
Country of Publication:
United States
Language:
English

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BENCHMARKS
BURNUP
BWR TYPE REACTORS
Boiling Water Reactor (BWR)
CALCULATION METHODS
CRITICALITY
MIXED OXIDE FUELS
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
PWR TYPE REACTORS
Pressurized Water Reactor (PWR) Fuel
REACTOR SAFETY