Search Results - "Sugino, Kazuteru"
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Cross-section-induced uncertainty evaluation of MA sample irradiation test calculations with consideration of dosimeter data
Published in Annals of nuclear energy (01-08-2019)“…•Modified burnup sensitivity coefficients for sample irradiation test data calculation.•Effectiveness for validation and improvement of the minor actinide…”
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A new cross section adjustment method of removing systematic errors in fast reactors
Published in Annals of nuclear energy (01-11-2017)“…•Systematic errors included in measurements and calculation are estimated by using the bias factors.•The systematic errors are removed in the new cross section…”
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Verification of a Nuclear Analysis System for Fast Reactors using BFS-62 Critical Experiment
Published in Journal of nuclear science and technology (01-12-2004)“…Critical experiments have been analyzed to verify a nuclear analysis system for fast reactors used in Japan Nuclear Cycle Development Institute (JNC). The…”
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An investigation on the control rod homogenization method for next-generation fast reactor cores
Published in Annals of nuclear energy (01-11-2021)“…A Japanese next-generation fast reactor core design adopts the reaction rate ratio preservation (RRRP) method for control rod homogenization with a super-cell…”
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JENDL-4.0 Benchmarking for Fission Reactor Applications
Published in Journal of nuclear science and technology (01-02-2011)“…Benchmark testing for the newly developed Japanese evaluated nuclear data library JENDL-4.0 is carried out by using a huge amount of integral data. Benchmark…”
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Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses
Published in Journal of nuclear science and technology (01-08-2006)“…A cell calculation code SLAROM-UF has been developed for fast reactor analyses to produce effective cross sections with high accuracy in practical computing…”
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JENDL-4.0 Benchmarking for Fission Reactor Applications
Published in Journal of nuclear science and technology (01-02-2011)“…Benchmark testing for the newly developed Japanese evaluated nuclear data library JENDL-4.0 is carried out by using a huge amount of integral data. Benchmark…”
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8
Effect of Polynomial Expansion Order of Intranode Flux Treatment in Nodal SN Transport Calculation Code NSHEX for Large-Size Fast Power Reactor Core Analysis
Published in Journal of nuclear science and technology (01-03-2011)“…The nodal discrete ordinates (SN) transport calculation code for three-dimensional hexagonal geometry NSHEX treats intranode flux distribution using a…”
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9
Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses
Published in Journal of nuclear science and technology (01-08-2006)“…A cell calculation code SLAROM-UF has been developed for fast reactor analyses to produce effective cross sections with high accuracy in practical computing…”
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10
Effect of Polynomial Expansion Order of Intranode Flux Treatment in Nodal SN Transport Calculation Code NSHEX for Large-Size Fast Power Reactor Core Analysis
Published in Journal of nuclear science and technology (01-03-2011)“…The nodal discrete ordinates (S N ) transport calculation code for three-dimensional hexagonal geometry NSHEX treats intranode flux distribution using a…”
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Effect of Polynomial Expansion Order of Intranode Flux Treatment in Nodal S sub(N) Transport Calculation Code NSHEX for Large-Size Fast Power Reactor Core Analysis
Published in Journal of nuclear science and technology (01-01-2011)“…The nodal discrete ordinates (S sub(N)) transport calculation code for three-dimensional hexagonal geometry NSHEX treats intranode flux distribution using a…”
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Comparison and sensitivity analysis of the core characteristics of a sodium-cooled fast breeder reactor with 750 MWe output evaluated by JENDL-4.0 and ADJ2000R
Published in Journal of nuclear science and technology (03-04-2014)“…Core characteristics of a sodium-cooled fast breeder reactor (FBR) with 750 MWe output using highly decontaminated uranium and plutonium and highly…”
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Development of a Unified Cross-section Set ADJ2000 based on Adjustment Technique for Fast Reactor Analysis
Published in Journal of nuclear science and technology (01-08-2002)“…A unified cross-section set, ADJ2000, which combined wide range of integral experimental information with differential nuclear data JENDL-3.2, has been…”
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15
Verification of a Nuclear Analysis System for Fast Reactors using BFS-62 Critical Experiment
Published in Journal of nuclear science and technology (01-12-2004)“…Critical experiments have been analyzed to verify a nuclear analysis system for fast reactors used in Japan Nuclear Cycle Development Institute (JNC). The…”
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JENDL-3.2 Covariance File
Published in Journal of nuclear science and technology (01-08-2002)“…Covariances of neutron nuclear data have been estimated for 16 nuclides contained in JENDL-3.2. The physical quantities for which covariances are deduced are…”
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