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Fukushima, Masahiro; Okajima, Shigeaki*; Mukaiyama, Takehiko*
Journal of Nuclear Science and Technology, 61(4), p.478 - 497, 2024/04
Times Cited Count:3 Percentile:73.09(Nuclear Science & Technology)A series of integral experiments was conducted to evaluate the fission and the capture cross- sections of transuranic (TRU) nuclides at the fast critical facility FCA of the Japan Atomic Energy Agency (JAEA). The experiments were carried out using seven uranium-fueled assemblies of the FCA. The neutron energy spectra of the core regions were adjusted so as to change from an intermediate neutron spectrum to a fast neutron spectrum on an assembly-by-assembly basis. The integral data measured with these experimental configurations provide some neutron energy characteristics: 1) fission rate ratios (FRRs) of Np,
Pu,
Pu,
Am,
Am, and
Cm relative to
Pu by using absolutely calibrated fission chambers, 2) small sample reactivity worths (SRWs) of
Np,
Pu,
Pu,
Am, and
Am where oxide powders of around 15 to 20 grams were used, 3) criticalities, and 4) spectral indices such as fission rate ratios of
U relative to
U. In this paper, details of the SRW measurements are reported, and the latest Japanese Evaluated Nuclear Data Library JENDL-5 is tested by using the integral data obtained in systematically varied neutron energy spectra.
Okajima, Shigeaki; Fukushima, Masahiro; Mukaiyama, Takehiko*
Proceedings of International Conference on the Physics of Reactors, Nuclear Power; A Sustainable Resource (PHYSOR 2008) (CD-ROM), 7 Pages, 2008/09
To validate the reliability of nuclear data of transuranium (TRU) in the evaluated nuclear data libraries, JENDL-3.3, ENDF/B-7.0 and JEFF-3.1, a benchmark test was performed by analyzing a series of central fission rate ratios of these nuclides (CFRR) measured at the Fast Critical Assembly (FCA) of JAEA. In the test a Monte Carlo calculation code is used. C/E values are compared between these data libraries.
Tsujimoto, Kazufumi; Kono, Nobuaki; Shinohara, Nobuo; Sakurai, Takeshi; Nakahara, Yoshinori; Mukaiyama, Takehiko; Raman, S.*
Nuclear Science and Engineering, 144(2), p.129 - 141, 2003/06
To evaluate neutron cross-section data of minor actinides, separated actinide samples and dosimetry samples were irradiated at the Dounreay Prototype Fast Reactor for 492 effective full power days. Based on the burnup calculations of major actinide and dosimetry samples, the neutron flux distribution and the flux level were adjusted at the locations where minor actinide samples were irradiated. The burnup calculations were carried out for minor actinides using the determined flux distribution and flux level. This paper discusses the burnup calculations and the validation of minor actinide cross-section data in evaluated nuclear data libraries. We find that we can obtain reliable FIMA (fission per initial metallic atom) values by using the Nd method except that the uncertainties in the FIMA values are large for
U,
Pu, Am isotopes, and Cm isotopes because the
Nd yields are known poorly for these isotopes and are probably overestimated. For these isotopes, measurements to improve the fission-yield data are needed. We also find that, in general, the JENDL-3.2 nuclear data for the minor actinides are adequate for the conceptual design study of transmutation systems. But, there are some nuclides (especially
Pu and
Pu) for which new measurements are needed particulary if the minor actinides constitute a major part of the nuclear fuel.
Tsujimoto, Kazufumi; Kono, Nobuaki; Shinohara, Nobuo; Sakurai, Takeshi; Nakahara, Yoshinori; Mukaiyama, Takehiko*; Raman, S.*
Nuclear Science and Engineering, 144(2), p.129 - 141, 2003/06
Times Cited Count:11 Percentile:58.72(Nuclear Science & Technology)no abstracts in English
Shinohara, Nobuo; Kono, Nobuaki; Nakahara, Yoshinori; Tsujimoto, Kazufumi; Sakurai, Takeshi; Mukaiyama, Takehiko*; Raman, S.*
Nuclear Science and Engineering, 144(2), p.115 - 128, 2003/06
no abstracts in English
Shinohara, Nobuo; Kono, Nobuaki; Nakahara, Yoshinori; Tsujimoto, Kazufumi; Sakurai, Takeshi; Mukaiyama, Takehiko*; Raman, S.*
Nuclear Science and Engineering, 144(2), p.115 - 128, 2003/06
Times Cited Count:13 Percentile:61.41(Nuclear Science & Technology)no abstracts in English
Mukaiyama, Takehiko
Genshikaku Kenkyu, 46(2), p.47 - 73, 2001/06
no abstracts in English
Mukaiyama, Takehiko; Takizuka, Takakazu; Mizumoto, Motoharu; Ikeda, Yujiro; Ogawa, Toru; Hasegawa, Akira; Takada, Hiroshi; Takano, Hideki
Progress in Nuclear Energy, 38(1-2), p.107 - 134, 2001/02
Times Cited Count:69 Percentile:96.92(Nuclear Science & Technology)no abstracts in English
Mukaiyama, Takehiko
Genshiryoku Shisutemu Nyusu, 11(1), p.5 - 13, 2000/06
no abstracts in English
Mukaiyama, Takehiko
Dai-38-kai Genshiryoku Sogo Shimpojium Rombunshu, p.1 - 9, 2000/05
no abstracts in English
Mukaiyama, Takehiko
Genshikaku Kenkyu, 44(6), p.23 - 32, 2000/04
no abstracts in English
Mukaiyama, Takehiko
EUR-19943-EN, p.129 - 138, 2000/00
no abstracts in English
Mukaiyama, Takehiko
RIST News, (28), p.3 - 11, 1999/09
no abstracts in English
Mukaiyama, Takehiko
Mirai, (6), p.40 - 43, 1999/07
no abstracts in English
Mukaiyama, Takehiko
Chuseishi Kagaku; NSA/Commentaries, No.7, p.1 - 2, 1999/06
no abstracts in English
Mukaiyama, Takehiko; Wakabayashi, Toshio*
Nihon Genshiryoku Gakkai-Shi, 41(6), p.713 - 714, 1999/06
no abstracts in English
Ogawa, Hironobu; Mukaiyama, Takehiko
JAERI-Tech 99-041, 188 Pages, 1999/05
no abstracts in English
Ogawa, Hironobu; Mukaiyama, Takehiko
JAERI-Tech 99-035, 106 Pages, 1999/03
no abstracts in English
Mukaiyama, Takehiko
Proceedings of the 3rd International Conference on Accelerator Driven Transmutation Technologies and Applications (CD-ROM), 12 Pages, 1999/00
no abstracts in English
Maekawa, Hiroshi; Mukaiyama, Takehiko; Yamane, Tsuyoshi; ; ; Suzuki, Atsuyuki*; Takeda, Renzo*; ; Kawashima, Masatoshi*; ; et al.
Nihon Genshiryoku Gakkai-Shi, 40(12), p.963 - 965, 1998/12
no abstracts in English