Benchmark Development in Support of Generation-IV Reactor Validation (IRPhEP 2010 Handbook)

Bess, John D.; Briggs, J. Blair

Title: Benchmark Development in Support of Generation-IV Reactor Validation (IRPhEP 2010 Handbook)

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Abstract

The March 2010 edition of the International Reactor Physics Experiment Evaluation Project (IRPhEP) Handbook includes additional benchmark data that can be implemented in the validation of data and methods for Generation IV (GEN-IV) reactor designs. Evaluations supporting sodium-cooled fast reactor (SFR) efforts include the initial isothermal tests of the Fast Flux Test Facility (FFTF) at the Hanford Site, the Zero Power Physics Reactor (ZPPR) 10B and 10C experiments at the Idaho National Laboratory (INL), and the burn-up reactivity coefficient of Japan’s JOYO reactor. An assessment of Russia’s BFS-61 assemblies at the Institute of Physics and Power Engineering (IPPE) provides additional information for lead-cooled fast reactor (LFR) systems. Benchmarks in support of the very high temperature reactor (VHTR) project include evaluations of the HTR-PROTEUS experiments performed at the Paul Scherrer Institut (PSI) in Switzerland and the start-up core physics tests of Japan’s High Temperature Engineering Test Reactor. The critical configuration of the Power Burst Facility (PBF) at the INL which used ternary ceramic fuel, U(18)O2-CaO-ZrO2, is of interest for fuel cycle research and development (FCR&D) and has some similarities to “inert-matrix” fuels that are of interest in GEN-IV advanced reactor design. Two additional evaluations were revised to include additional evaluated experimentalmore »« less

Authors:

Bess, John D. ^[1]; Briggs, J. Blair ^[1]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Publication Date:: Sun Jun 13 00:00:00 EDT 2010

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)

OSTI Identifier:: 983354

Report Number(s):: INL/CON-09-17384
TRN: US1004455

DOE Contract Number:: AC07-05ID14517

Resource Type:: Conference

Resource Relation:: Conference: 2010 International Congress on Advances in Nuclear Power Plants (ICAPP '10), San Diego, CA (United States), 13-17 Jun 2010

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BENCHMARKS; CERAMICS; CONFIGURATION; DESIGN; ETR REACTOR; FAST REACTORS; FFTF REACTOR; FUEL CYCLE; HEAVY WATER; JOYO REACTOR; NUCLEAR POWER PLANTS; PHYSICS; REACTIVITY COEFFICIENTS; REACTOR PHYSICS; RESEARCH REACTORS; START-UP; VALIDATION; Nuclear Criticality Safety Program (NCSP); Benchmark; Generation IV (GEN-IV) Reactor; International Reactor Physics Experiment Evaluation Project (IRPhEP) Handbook; Fast Flux Test Facility (FFTF); Zero Power Physics Reactor (ZPPR); Sodium-Cooled Fast Reactor (SFR); High Flux Reactor (RHF); Light Water Reactor (LWR); Heavy Water Reactor (HWR)

Citation Formats


                    Bess, John D., and Briggs, J. Blair. Benchmark Development in Support of Generation-IV Reactor Validation (IRPhEP 2010 Handbook).  United States: N. p., 2010. 
        Web.

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                    Bess, John D., & Briggs, J. Blair. Benchmark Development in Support of Generation-IV Reactor Validation (IRPhEP 2010 Handbook).  United States.

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                    Bess, John D., and Briggs, J. Blair. 2010.  
        "Benchmark Development in Support of Generation-IV Reactor Validation (IRPhEP 2010 Handbook)".  United States.  https://www.osti.gov/servlets/purl/983354.

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@article{osti_983354,

  title        = {Benchmark Development in Support of Generation-IV Reactor Validation (IRPhEP 2010 Handbook)},

  author       = {Bess, John D. and Briggs, J. Blair},

  abstractNote = {The March 2010 edition of the International Reactor Physics Experiment Evaluation Project (IRPhEP) Handbook includes additional benchmark data that can be implemented in the validation of data and methods for Generation IV (GEN-IV) reactor designs. Evaluations supporting sodium-cooled fast reactor (SFR) efforts include the initial isothermal tests of the Fast Flux Test Facility (FFTF) at the Hanford Site, the Zero Power Physics Reactor (ZPPR) 10B and 10C experiments at the Idaho National Laboratory (INL), and the burn-up reactivity coefficient of Japan’s JOYO reactor. An assessment of Russia’s BFS-61 assemblies at the Institute of Physics and Power Engineering (IPPE) provides additional information for lead-cooled fast reactor (LFR) systems. Benchmarks in support of the very high temperature reactor (VHTR) project include evaluations of the HTR-PROTEUS experiments performed at the Paul Scherrer Institut (PSI) in Switzerland and the start-up core physics tests of Japan’s High Temperature Engineering Test Reactor. The critical configuration of the Power Burst Facility (PBF) at the INL which used ternary ceramic fuel, U(18)O2-CaO-ZrO2, is of interest for fuel cycle research and development (FCR&D) and has some similarities to “inert-matrix” fuels that are of interest in GEN-IV advanced reactor design. Two additional evaluations were revised to include additional evaluated experimental data, in support of light water reactor (LWR) and heavy water reactor (HWR) research; these include reactor physics experiments at Brazil’s IPEN/MB-01 Research Reactor Facility and the French High Flux Reactor (RHF), respectively. The IRPhEP Handbook now includes data from 45 experimental series (representing 24 reactor facilities) and represents contributions from 15 countries. These experimental measurements represent large investments of infrastructure, experience, and cost that have been evaluated and preserved as benchmarks for the validation of methods and collection of data in support of current and future reactor design and development.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/983354},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Sun Jun 13 00:00:00 EDT 2010},

  month        = {Sun Jun 13 00:00:00 EDT 2010}

}

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