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Journal Articles

A Review of activities for risk-informed criticality safety assessment in U.K., U.S.A. and Japan

Tamaki, Hitoshi; Naito, Yoshitaka*; Suzuki, Tadakazu*; Mitsuhashi, Takeshi*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 50(2), p.97 - 102, 2008/02

no abstracts in English

JAEA Reports

Study on the prediction accuracy of nuclide generation and depletion with JENDL

Okumura, Keisuke; Oki, Shigeo*; Yamamoto, Munenari*; Matsumoto, Hideki*; Ando, Yoshihira*; Tsujimoto, Kazufumi; Sasahara, Akihiro*; Katakura, Junichi; Matsumura, Tetsuo*; Aoyama, Takafumi*; et al.

JAERI-Research 2004-025, 154 Pages, 2005/01

JAERI-Research-2004-025.pdf:19.46MB

This report summarizes the activity (FY2000-2003) of Working Group (WG) on Evaluation of Nuclide Generation and Depletion under Subcommittee on Nuclear Fuel Cycle of Japanese Nuclear Data Committee. In the WG, analyses of Post Irradiation Examinations have been carried out for UO$$_{2}$$ and MOX fuels irradiated in PWRs, BWRs and FBRs, and for actinide samples irradiated in fast reactors, by using ORIGEN or more detailed calculation codes with their libraries based on JENDL-3.2, JENDL-3.3 and other foreign nuclear data files. From these results, current prediction accuracy and problems for evaluation of nuclide generation and depletion are discussed. Furthermore, this report covers other products of our activity; development of the ORIGEN libraries for PWR, BWR and FBR based on JENDL-3.3, study on introduction of neutron spectrum index to ORIGEN calculations, and results of questionnaire survey on desirable accuracy of ORIGEN calculations.

JAEA Reports

OECD/NEA burnup credit criticality benchmarks phase IIIB; Burnup calculations of BWR fuel assemblies for storage and transport

Okuno, Hiroshi; Naito, Yoshitaka*; Suyama, Kenya

JAERI-Research 2002-001, 181 Pages, 2002/02

JAERI-Research-2002-001.pdf:10.89MB

The report describes the final results of the Phase IIIB Benchmark conducted by the Expert Group on Burnup Credit Criticality Safety under the auspices of the OECD/NEA. The Benchmark was intended to compare the predictability of current computer code and data library combinations for the atomic number densities of an irradiated BWR fuel assembly model, which was irradiated under specific power of 25.6 MW/tHM up to 40 GWd/tHM and cooled for five years. The void fraction was assumed to be uniform and constant, at 0, 40 and 70%, during burnup. In total, 16 results were submitted from 13 institutes of 7 countries. The calculated densities of 12 actinides and 20 fission product nuclides were found mostly within a range of +- 10% relative to the average, although some results, esp. 155Eu and gadolinium isotopes, exceeded the band. Pin-wise burnup results agreed well among the participants. The results in the multiplication factor also accorded well with each other for void fractions of 0 and 40%; however some results deviated from the average noticeably for the void fraction of 70%.

Journal Articles

Education program for criticality safety with Monte Carlo method

Sakurai, Kiyoshi; Ueki, Kotaro*; Naito, Yoshitaka*

Nihon Genshiryoku Gakkai-Shi, 43(3), p.219 - 220, 2001/03

no abstracts in English

JAEA Reports

Report of "Monte Carlo Calculation Summer Seminar"

Sakurai, Kiyoshi; Kume, Etsuo; Yatabe, Shigeru*; Maekawa, Fujio; Yamamoto, Toshihiro; Nagaya, Yasunobu; Mori, Takamasa; Ueki, Kotaro*; Naito, Yoshitaka*

JAERI-Review 2000-034, 133 Pages, 2001/02

JAERI-Review-2000-034.pdf:7.69MB

no abstracts in English

Journal Articles

Report of Monte Carlo calculation summer seminar

Sakurai, Kiyoshi; Kume, Etsuo; Yatabe, Shigeru*; Maekawa, Fujio; Yamamoto, Toshihiro; Nagaya, Yasunobu; Mori, Takamasa; Ueki, Kotaro*; Naito, Yoshitaka*

Nihon Genshiryoku Gakkai-Shi, 42(10), p.1062 - 1065, 2000/10

no abstracts in English

Journal Articles

Methodology of Monte Carlo research

Sakurai, Kiyoshi; Ueki, Kotaro*; Naito, Yoshitaka*

Nihon Genshiryoku Gakkai-Shi, 42(10), p.1048 - 1049, 2000/10

no abstracts in English

JAEA Reports

OECD/NEA burnup credit criticality benchmarks phase IIIA; Criticality calculations of BWR spent fuel assemblies in storage and transport

Okuno, Hiroshi; Naito, Yoshitaka*; Ando, Yoshihira*

JAERI-Research 2000-041, 179 Pages, 2000/09

JAERI-Research-2000-041.pdf:6.11MB

no abstracts in English

Journal Articles

MCNP高温ライブラリーの信頼性チェックの考え方

Sakurai, Kiyoshi; Maekawa, Fujio; Yamamoto, Toshihiro; Mori, Takamasa; Naito, Yoshitaka*

Kaku Deta Nyusu (Internet), (66), p.91 - 92, 2000/06

no abstracts in English

Journal Articles

Overview of recent research activities of Monte Carlo simulation in Japan

Sakurai, Kiyoshi; Yamamoto, Toshihiro; Ueki, Kotaro*; Mori, Takamasa; Nomura, Yasushi; Naito, Yoshitaka*

Journal of Nuclear Science and Technology, 37(Suppl.1), p.446 - 448, 2000/03

no abstracts in English

Journal Articles

On the development of Monte Carlo calculation

Sakurai, Kiyoshi; Ueki, Kotaro*; Naito, Yoshitaka*

Nihon Genshiryoku Gakkai-Shi, 42(2), p.114 - 115, 2000/02

no abstracts in English

JAEA Reports

Development of automatic editing system for MCNP library "autonj"

Maekawa, Fujio; Sakurai, Kiyoshi; Kosako, Kazuaki*; Kume, Etsuo; Kawasaki, Nobuo*; Nomura, Yasushi; Naito, Yoshitaka*

JAERI-Data/Code 99-048, p.52 - 0, 1999/12

JAERI-Data-Code-99-048.pdf:2.34MB

no abstracts in English

Journal Articles

Continuous energy Monte Carlo code MCNP-4C and preparation in Japan

Sakurai, Kiyoshi; Maekawa, Fujio; Kume, Etsuo; Nomura, Yasushi; Naito, Yoshitaka*

Nihon Genshiryoku Gakkai-Shi, 41(9), P. 924, 1999/09

no abstracts in English

Journal Articles

Present status of Monte Carlo simulation for neutron and photon transport

Ueki, Kotaro*; Mori, Takamasa; Sakurai, Kiyoshi; Nakakawa, Masayuki; *

Nihon Genshiryoku Gakkai-Shi, 41(6), p.614 - 627, 1999/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

International studies on burnup credit criticality safety by an OECD/NEA working group, 2; Calculation benchmarks for BWR spent fuels

; *; Suyama, Kenya; Ando, Yoshihira*

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 2, p.566 - 575, 1999/00

no abstracts in English

Journal Articles

Fault-tree analysis of criticality in a pulsed column of a typical reprocessing facility

Nomura, Yasushi; Naito, Yoshitaka

Nuclear Technology, 121(1), p.3 - 12, 1998/01

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Numerical validation of a modified neutron source multiplication method using a calculated eigenvalue

Yamamoto, Toshihiro; Sakurai, Kiyoshi; *

Annals of Nuclear Energy, 25(9), p.599 - 607, 1998/00

 Times Cited Count:1 Percentile:15.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Estimation of subcriticality with the computed values; Analysis using MCNP of experiment on coupled cores

Sakurai, Kiyoshi; Yamamoto, Toshihiro; Arakawa, Takuya*; *

Nihon Genshiryoku Gakkai-Shi, 40(5), p.380 - 386, 1998/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effect of long-term storage of LWR spent fuel on Pu-thermal fuel cycle

Kurosawa, Masayoshi; Naito, Yoshitaka; Suyama, Kenya; *; Suzuki, Katsuo*; *

Nihon Genshiryoku Gakkai-Shi, 40(6), p.486 - 494, 1998/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Accurate Estimation of Subcriticality Using Indirect Bias Estimation Method,(II) Applications

Sakurai, Kiyoshi; Yamamoto, Toshihiro; Arakawa, Takuya*; Naito, Yoshitaka

Journal of Nuclear Science and Technology, 34(6), p.544 - 550, 1997/06

 Times Cited Count:2 Percentile:23.04(Nuclear Science & Technology)

no abstracts in English

147 (Records 1-20 displayed on this page)