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JAEA Reports

Nuclear criticality benchmark analyses on TRIGA-type reactor systems by using continuous-energy Monte Carlo code MVP with JENDL-5

Yanagisawa, Hiroshi; Umeda, Miki; Motome, Yuiko; Murao, Hiroyuki

JAEA-Technology 2022-030, 80 Pages, 2023/02

JAEA-Technology-2022-030.pdf:2.57MB
JAEA-Technology-2022-030(errata).pdf:0.11MB

Nuclear criticality benchmark analyses were carried out for TRIGA-type reactor systems in which uranium-zirconium hydride fuel rods are loaded by using the continuous-energy Monte Carlo code MVP with the evaluated nuclear data library JENDL-5. The analyses cover two sorts of benchmark data, the IEU-COMP-THERM-003 and IEU-COMP-THERM-013 in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook, and effective neutron multiplication factors, reactivity worths for control rods etc. were calculated by JENDL-5 in comparison with those by the previous version of JENDL. As the results, it was confirmed that the effective neutron multiplication factors obtained by JENDL-5 were 0.4 to 0.6% greater than those by JENDL-4.0, and that there were no significant differences in the calculated reactivity worths by between JENDL-5 and JENDL-4.0. Those results are considered to be helpful for the confirmation of calculation accuracy in the analyses on NSRR control rod worths, which are planned in the future.

Journal Articles

An Investigation on the control rod homogenization method for next-generation fast reactor cores

Takino, Kazuo; Sugino, Kazuteru; Oki, Shigeo

Annals of Nuclear Energy, 162, p.108454_1 - 108454_7, 2021/11

 Times Cited Count:1 Percentile:15.7(Nuclear Science & Technology)

Journal Articles

Validation of the nuclear design code system for the HTTR using the criticality assembly VHTRC

Fujimoto, Nozomu; Nojiri, Naoki; Yamashita, Kiyonobu*

Nuclear Engineering and Design, 233(1-3), p.155 - 162, 2004/10

 Times Cited Count:2 Percentile:17.16(Nuclear Science & Technology)

The HTTR uses low-enriched uranium fuel with burnable poison rod. For validation of the nuclear design code system for the HTTR, a critical assembly of VHTRC had been constructed. The calculation uncertainties of effective multiplication factor, neutron flux distribution, burnable poison reactivity worth, and control rod worth, temperature coefficients were evaluated. Calculation accuracy of a Monte Carlo code is also evaluated.

Journal Articles

Characteristic test of initial HTTR core

Nojiri, Naoki; Shimakawa, Satoshi; Fujimoto, Nozomu; Goto, Minoru

Nuclear Engineering and Design, 233(1-3), p.283 - 290, 2004/10

 Times Cited Count:12 Percentile:61.44(Nuclear Science & Technology)

This paper describes the results of core physics test in start-up and power-up of the HTTR. The tests were conducted in order to ensure performance and safety of the high temperature gas cooled reactor, and was carried out to measure the critical approach, the excess reactivity, the shutdown margin, the control rod worth, the reactivity coefficient, the neutron flux distribution and the power distribution. The expected core performance and the required reactor safety characteristics were verified from the results of measurements and calculations.

JAEA Reports

Preliminary analyses for HTTR's start-up physics tests by HTTR nuclear characteristics evaluation code system

Fujimoto, Nozomu; Nojiri, Naoki; Nakano, Masaaki*; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu

JAERI-Tech 98-021, 66 Pages, 1998/06

JAERI-Tech-98-021.pdf:2.63MB

no abstracts in English

Journal Articles

The Present active status of domestic critical assemblies and the perspective for their future, 2-4; Very high temperature reactor critical assembly (VHTRC)

Akino, Fujiyoshi; Yamane, Tsuyoshi

Nihon Genshiryoku Gakkai-Shi, 40(4), p.262 - 264, 1998/00

no abstracts in English

JAEA Reports

Measurement of reactivity worths of Sm,Cs,Gd,Nd,Rh,Eu,B and Er aqueous solution samples

Komuro, Yuichi; Suzaki, Takenori; *; Sakurai, Kiyoshi; Horiki, Oichiro*

JAERI-Research 97-088, 19 Pages, 1997/11

JAERI-Research-97-088.pdf:0.86MB

no abstracts in English

Journal Articles

Measurement of flux tilt and eigenvalue separation in axially decoupled core

Ando, Masaki; *; Nishina, Kojiro*; *

Journal of Nuclear Science and Technology, 34(5), p.445 - 453, 1997/05

 Times Cited Count:6 Percentile:47.9(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental verification and analysis of neutron streaming effect through void holes for control rod insertion in HTTR

Akino, Fujiyoshi; Takeuchi, Motoyoshi; Ono, Toshihiko; Kaneko, Yoshihiko

Journal of Nuclear Science and Technology, 34(2), p.185 - 192, 1997/02

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

no abstracts in English

Journal Articles

Measurement of reactivity worths of natural Sm, Cs, Gd, Nd, Rh, Eu, B and Er

Komuro, Yuichi; ; Sakurai, Kiyoshi; Yamamoto, Toshihiro; Suzaki, Takenori; Horiki, Oichiro*; Nitta, Kazuo*

PHYSOR 96: Int. Conf. on the Physics of Reactors, 1, p.L120 - L129, 1996/00

no abstracts in English

Journal Articles

Analysis of control rod reactivity worths for AVR power plant at cold and hot conditions

Yamashita, Kiyonobu; Murata, Isao; Shindo, Ryuichi; *; H.Werner*

Journal of Nuclear Science and Technology, 31(5), p.470 - 478, 1994/05

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

no abstracts in English

JAEA Reports

Basic experiments of reactor physics using the critical assembly TCA

Obara, Toru*; Nakajima, Ken; *; Sekimoto, Hiroshi*; Suzaki, Takenori

JAERI-M 94-004, 40 Pages, 1994/02

JAERI-M-94-004.pdf:1.04MB

no abstracts in English

Journal Articles

Neutronics properties of JMTR LEU core

Nagaoka, Yoshiharu; Saito, Minoru;

Transactions of the American Nuclear Society, 66, p.454 - 455, 1992/11

no abstracts in English

Journal Articles

Selected reactor physics phenomena observed during N.S.Mutsu power-up tests

; Miyoshi, Yoshinori; *; *; ;

Proc. of the Int. Conf. on Nuclear Power Plant Operations; Ready for 2000, p.435 - 441, 1992/00

no abstracts in English

JAEA Reports

Experimental study of power distribution in FCA XV cores with half-inserted B$$_{4}$$C control rod

Oigawa, Hiroyuki; Osugi, Toshitaka; Ono, Akio; ; *

JAERI-M 91-096, 39 Pages, 1991/06

JAERI-M-91-096.pdf:0.85MB

no abstracts in English

Journal Articles

Experimental study on reactivity worth for absorber material in high conversion light water reactor using FCA-HCLWR core fueled with enriched uranium

Okajima, Shigeaki; Osugi, Toshitaka; Sakurai, Takeshi; *

Journal of Nuclear Science and Technology, 27(10), p.950 - 959, 1990/10

no abstracts in English

Journal Articles

Development and valiation of nuclear design code system for High Temperature Engineering Test Reactor (HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao

The Safety,Status and Future of Non-Commercial Reactors and Irradiation Facilities,Vol. 1, p.350 - 358, 1990/09

no abstracts in English

JAEA Reports

Journal Articles

Analysis of SHE critical experiments by neutronic design codes for experimental very high temperature reactor

; ; ; *

Journal of Nuclear Science and Technology, 22(5), p.358 - 370, 1985/05

 Times Cited Count:13 Percentile:81.92(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

32 (Records 1-20 displayed on this page)