Large Core Code Evaluation Working Group Benchmark Problem Four: neutronics and burnup analysis of a large heterogeneous fast reactor. Part 1. Analysis of benchmark results. [LMFBR]

Cowan, C L; Protsik, R; Lewellen, J W

doi:10.2172/6931395

Title: Large Core Code Evaluation Working Group Benchmark Problem Four: neutronics and burnup analysis of a large heterogeneous fast reactor. Part 1. Analysis of benchmark results. [LMFBR]

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Abstract

The Large Core Code Evaluation Working Group Benchmark Problem Four was specified to provide a stringent test of the current methods which are used in the nuclear design and analyses process. The benchmark specifications provided a base for performing detailed burnup calculations over the first two irradiation cycles for a large heterogeneous fast reactor. Particular emphasis was placed on the techniques for modeling the three-dimensional benchmark geometry, and sensitivity studies were carried out to determine the performance parameter sensitivities to changes in the neutronics and burnup specifications. The results of the Benchmark Four calculations indicated that a linked RZ-XY (Hex) two-dimensional representation of the benchmark model geometry can be used to predict mass balance data, power distributions, regionwise fuel exposure data and burnup reactivities with good accuracy when compared with the results of direct three-dimensional computations. Most of the small differences in the results of the benchmark analyses by the different participants were attributed to ambiguities in carrying out the regionwise flux renormalization calculations throughout the burnup step.

Authors:

Cowan, C L; Protsik, R; Lewellen, J W ^[1]

eds.

Publication Date:: Sun Jan 01 00:00:00 EST 1984

Research Org.:: General Electric Co., Sunnyvale, CA (USA). Advanced Reactor Systems Dept.; Department of Energy, Washington, DC (USA). Div. of Reactor Research and Technology

OSTI Identifier:: 6931395

Report Number(s):: DOE/NBM-4014795
ON: DE84014795

Resource Type:: Technical Report

Resource Relation:: Other Information: Portions are illegible in microfiche products. Original copy available until stock is exhausted

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LMFBR TYPE REACTORS; REACTOR CORES; BURNUP; POWER DISTRIBUTION; REACTIVITY WORTHS; BENCHMARKS; COMPUTER CALCULATIONS; REACTOR KINETICS; THEORETICAL DATA; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; BREEDER REACTORS; DATA; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; INFORMATION; KINETICS; LIQUID METAL COOLED REACTORS; NUMERICAL DATA; REACTOR COMPONENTS; REACTORS; 210500* - Power Reactors, Breeding

Citation Formats


                    Cowan, C L, Protsik, R, and Lewellen, J W. Large Core Code Evaluation Working Group Benchmark Problem Four: neutronics and burnup analysis of a large heterogeneous fast reactor. Part 1. Analysis of benchmark results. [LMFBR].  United States: N. p., 1984. 
        Web.  doi:10.2172/6931395.

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                    Cowan, C L, Protsik, R, & Lewellen, J W. Large Core Code Evaluation Working Group Benchmark Problem Four: neutronics and burnup analysis of a large heterogeneous fast reactor. Part 1. Analysis of benchmark results. [LMFBR].  United States.  https://doi.org/10.2172/6931395

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                    Cowan, C L, Protsik, R, and Lewellen, J W. 1984.  
        "Large Core Code Evaluation Working Group Benchmark Problem Four: neutronics and burnup analysis of a large heterogeneous fast reactor. Part 1. Analysis of benchmark results. [LMFBR]".  United States.  https://doi.org/10.2172/6931395.  https://www.osti.gov/servlets/purl/6931395.

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@article{osti_6931395,

  title        = {Large Core Code Evaluation Working Group Benchmark Problem Four: neutronics and burnup analysis of a large heterogeneous fast reactor. Part 1. Analysis of benchmark results. [LMFBR]},

  author       = {Cowan, C L and Protsik, R and Lewellen, J W},

  abstractNote = {The Large Core Code Evaluation Working Group Benchmark Problem Four was specified to provide a stringent test of the current methods which are used in the nuclear design and analyses process. The benchmark specifications provided a base for performing detailed burnup calculations over the first two irradiation cycles for a large heterogeneous fast reactor. Particular emphasis was placed on the techniques for modeling the three-dimensional benchmark geometry, and sensitivity studies were carried out to determine the performance parameter sensitivities to changes in the neutronics and burnup specifications. The results of the Benchmark Four calculations indicated that a linked RZ-XY (Hex) two-dimensional representation of the benchmark model geometry can be used to predict mass balance data, power distributions, regionwise fuel exposure data and burnup reactivities with good accuracy when compared with the results of direct three-dimensional computations. Most of the small differences in the results of the benchmark analyses by the different participants were attributed to ambiguities in carrying out the regionwise flux renormalization calculations throughout the burnup step.},

  doi          = {10.2172/6931395},

  url          = {https://www.osti.gov/biblio/6931395},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Sun Jan 01 00:00:00 EST 1984},

  month        = {Sun Jan 01 00:00:00 EST 1984}

}

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