Search Results - "Sugino, Kazuteru"

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  1. 1

    Cross-section-induced uncertainty evaluation of MA sample irradiation test calculations with consideration of dosimeter data by Sugino, Kazuteru, Numata, Kazuyuki, Ishikawa, Makoto, Takeda, Toshikazu

    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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    Journal Article
  2. 2

    A new cross section adjustment method of removing systematic errors in fast reactors by Takeda, Toshikazu, Yokoyama, Kenji, Sugino, Kazuteru

    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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    Journal Article
  3. 3

    Verification of a Nuclear Analysis System for Fast Reactors using BFS-62 Critical Experiment by HAZAMA, Taira, SHONO, Akira, SUGINO, Kazuteru

    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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    Journal Article
  4. 4

    An investigation on the control rod homogenization method for next-generation fast reactor cores by Takino, Kazuo, Sugino, Kazuteru, Ohki, Shigeo

    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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    Journal Article
  5. 5

    JENDL-4.0 Benchmarking for Fission Reactor Applications by CHIBA, Go, OKUMURA, Keisuke, SUGINO, Kazuteru, NAGAYA, Yasunobu, YOKOYAMA, Kenji, KUGO, Teruhiko, ISHIKAWA, Makoto, OKAJIMA, Shigeaki

    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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    Journal Article
  6. 6

    Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses by HAZAMA, Taira, CHIBA, Go, SUGINO, Kazuteru

    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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    Journal Article
  7. 7

    JENDL-4.0 Benchmarking for Fission Reactor Applications by CHIBA, Go, OKUMURA, Keisuke, SUGINO, Kazuteru, NAGAYA, Yasunobu, YOKOYAMA, Kenji, KUGO, Teruhiko, ISHIKAWA, Makoto, OKAJIMA, Shigeaki

    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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    Journal Article
  8. 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 by SUGINO, Kazuteru, KUGO, Teruhiko

    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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    Journal Article
  9. 9

    Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses by HAZAMA, Taira, CHIBA, Go, SUGINO, Kazuteru

    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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    Journal Article
  10. 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 by SUGINO, Kazuteru, KUGO, Teruhiko

    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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    Journal Article
  11. 11
  12. 12

    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 by Sugino, Kazuteru, Kugo, Teruhiko

    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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    Journal Article
  13. 13

    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 by Ohgama, Kazuya, Ohki, Shigeo, Sugino, Kazuteru, Okubo, Tsutomu

    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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    Journal Article
  14. 14

    Development of a Unified Cross-section Set ADJ2000 based on Adjustment Technique for Fast Reactor Analysis by Ishikawa, Makoto, Sugino, Kazuteru, Sato, Wakaei, Numata, Kazuyuki

    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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    Journal Article
  15. 15

    Verification of a Nuclear Analysis System for Fast Reactors using BFS-62 Critical Experiment by HAZAMA, Taira, SHONO, Akira, SUGINO, Kazuteru

    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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    Journal Article
  16. 16

    JENDL-3.2 Covariance File by Shibata, Keiichi, Hasegawa, Akira, Iwamoto, Osamu, Chiba, Satoshi, Sugimoto, Masayoshi, Odano, Naoteru, Kawano, Toshihiko, Nakajima, Yutaka, Murata, Toru, Matsunobu, Hiroyuki, Oh, Youl Soo, Yokoyama, Kenji, Sugino, Kazuteru, Ishikawa, Makoto, Kosako, Kazuaki, Yamano, Naoki, Kanda, Yukinori

    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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    Journal Article