Development of the CPXSD Methodology for Generation of Fine-Group Libraries for Shielding Applications

Alpan, F. A.; Haghighat, Alireza

doi:10.13182/nse04-23

Cited by 16 publications

(3 citation statements)

References 4 publications

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“…The refinement of the energy group structures were conducted using the Contributon and Point-Wise Cross Section Driven (CPXSD) method which was developed by Alpan and Haghighat, 2005. The CPXSD method was derived based on the product of the forward and adjoint angular fluxes, and the point-wise cross section of important isotope/material of interest (see Eq.…”

Section: Methodsmentioning

confidence: 99%

Examination and refinement of fine energy group structure for high temperature reactor analysis

Ngeleka

Ivanov

Levine

2015

Annals of Nuclear Energy

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a b s t r a c tMulti-group energy structure SHEM-281 and -361 were refined using a Contributon and Point-Wise Cross Section Driven method (CPXSD). The Contributon and Point-Wise Cross Section Driven method was derived based on the product of the forward and adjoint angular fluxes, and the point-wise cross section of important isotope/material. It is an iterative method that selects effective fine-and broad-group energy structures for a problem of interest. The two selected criteria for determining fine energy group structure were 10 pcm relative deviation of Dk/k for k-effective and 1% relative deviation for reaction rates. The energy group structure refinement was subdivided into fast, epithermal and thermal regions. Firstly, the refinement was done for fast region and a new library was created and applied in the fuel cell unit until the target criteria's are met. Similar procedure was repeated for epithermal and thermal regions. The dominant parameters for each region are considered as required, fission reaction rate for fast region, absorption reaction rate for epithermal region and absorption and fission reaction rates for thermal region.

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Section: Methodsmentioning

confidence: 99%

Examination and refinement of fine energy group structure for high temperature reactor analysis

Ngeleka

Ivanov

Levine

2015

Annals of Nuclear Energy

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“…ALPAN-VII.0 was developed at Westinghouse for PWR internals and pressure vessel dosimetry applications, based on ENDF/B-VII.0 [8] and using the contributon and point-wise cross section driven methodology [9]. ALPAN-VII.0 contains crosssection sets with coupled 461-neutron, 42-gamma-ray-group and coupled 44-neutron, 20-gamma-ray group structures.…”

Section: Introductionmentioning

confidence: 99%

Comparison of Standard Light Water Reactor Cross-Section Libraries using the United States Nuclear Regulatory Commission Pressurized Water Reactor Standard Core Loading Benchmark Problem

Alpan

2016

EPJ Web of Conferences

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Abstract. This paper compares contemporary and historical light water reactor shielding and pressure vessel dosimetry cross-section libraries for a pressurized water reactor calculational benchmark problem with a standard out-in core loading. The calculational benchmark problem was developed at Brookhaven National Laboratory by the request of the U. S. Nuclear Regulatory Commission and used the Oak Ridge National Laboratory two-dimensional discrete ordinates code DORT and the BUGLE-93 cross-section library for the calculations. In this paper, a Westinghouse three-dimensional discrete ordinates code with parallel processing, the RAPTOR-M3G code was used. A variety of cross section libraries were used with RAPTOR-M3G including the BUGLE-93, BUGLE-96, and BUGLE-B7 cross-section libraries developed at Oak Ridge National Laboratory, and the broad-group ALPAN-VII.0 cross-section library developed at Westinghouse. In comparing the calculation-to-calculation reaction rates using the BUGLE-93 cross-section library at the thermal shield, pressure vessel, and cavity capsules, for eleven dosimetry reaction rates, a maximum relative difference of 5% was observed, with the exception of 65 Cu(n,2n) in the pressure vessel capsule that had a 90% relative difference with respect to the reference results. It is thought that the 65 Cu(n,2n) reaction rate reported in the reference for the pressure vessel capsule is not correct. In considering the libraries developed after BUGLE-93, a maximum relative difference of 12% was observed in reaction rates, with respect to the reference results, for 237 Np(n,f) in the cavity capsule using BUGLE-B7.

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“…The BUGLE-B7 library, the latest of the BUGLE libraries, has the same group structure of BUGLE-93 and BUGLE-96 and uses ENDF/B-VII.0. ALPAN-VII.0 was developed at Westinghouse for pressurized water reactor (PWR) internals and pressure vessel dosimetry applications, based on ENDF/B-VII.0 [8] and using the contributon and point-wise cross section driven methodology [9]. ALPAN-VII.0 contains crosssection sets with coupled 461-neutron, 42-gamma-ray-group and coupled 44-neutron, 20-gamma-ray group structures.…”

Section: Introductionmentioning

confidence: 99%

Comparison of Standard Light Water Reactor Cross-Section Libraries using the United States Nuclear Regulatory Commission Boiling Water Reactor Benchmark Problem

Alpan

2016

EPJ Web of Conferences

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Abstract. This paper describes a comparison of contemporary and historical light water reactor shielding and pressure vessel dosimetry cross-section libraries for a boiling water reactor calculational benchmark problem. The calculational benchmark problem was developed at Brookhaven National Laboratory by the request of the U. S. Nuclear Regulatory Commission. The benchmark problem was originally evaluated by Brookhaven National Laboratory using the Oak Ridge National Laboratory discrete ordinates code DORT and the BUGLE-93 cross-section library. In this paper, the Westinghouse RAPTOR-M3G three-dimensional discrete ordinates code was used. A variety of cross-section libraries were used with RAPTOR-M3G including the BUGLE93, BUGLE-96, and BUGLE-B7 cross-section libraries developed at Oak Ridge National Laboratory and ALPAN-VII.0 developed at Westinghouse. In comparing the calculated fast reaction rates using the four aforementioned cross-section libraries in the pressure vessel capsule, for six dosimetry reaction rates, a maximum relative difference of 8% was observed. As such, it is concluded that the results calculated by RAPTOR-M3G are consistent with the benchmark and further that the different vintage BUGLE cross-section libraries investigated are largely self-consistent.

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Development of the CPXSD Methodology for Generation of Fine-Group Libraries for Shielding Applications

Cited by 16 publications

References 4 publications

Examination and refinement of fine energy group structure for high temperature reactor analysis

Examination and refinement of fine energy group structure for high temperature reactor analysis

Comparison of Standard Light Water Reactor Cross-Section Libraries using the United States Nuclear Regulatory Commission Pressurized Water Reactor Standard Core Loading Benchmark Problem

Comparison of Standard Light Water Reactor Cross-Section Libraries using the United States Nuclear Regulatory Commission Boiling Water Reactor Benchmark Problem

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