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Okumura, Keisuke; Kojima, Kensuke; Tanaka, Kenichi*
JAEA-Conf 2015-003, p.43 - 47, 2016/03
In the safety assessment concerning disposal of radioactive wastes generated in the decommissioning of nuclear facilities, it is necessary to evaluate the radionuclide inventory produced by the activation of structured materials. For this purpose, we have to pay much attention to the activation of many impurities irradiated in various neutron spectra depending on their positions and materials. Therefore, accurate activation cross-section data are necessary for many nuclides and reactions. A new multi-group neutron activation cross-section library (MAXS) was developed based on the recent nuclear data JENDL-4.0 and JEFF-3.0/A to apply it to the activation calculations for the decommissioning of nuclear facilities. The library contains cross-sections and isomeric ratios for many reactions such as (n,
), (n,f), (n,2n), (n,3n), (n,p), (n,
), (n,d), (n,t), (n,n), (n,np), and so on, for 779 nuclides, in the 199-energy group structure of VITAMIN-B6.
Katakura, Junichi; Kataoka, Masaharu*; Suyama, Kenya; Jin, Tomoyuki*; Oki, Shigeo*
JAERI-Data/Code 2004-015, 115 Pages, 2004/11
JAERI-Data-Code-2004-015.pdf:16.52MB
A set of cross section libraries for ORIGEN2 code, ORLIBJ33, has been produced based on the latest Japanese Evaluated Nuclear Data Library JENDL-3.3. The produced libraries are for LWR's which include PWR, BWR and their MOX fuels. The libraries for FBR's are also produced. Using the libraries for LWR, comparisons with old libraries based on JENDL-3.2 were performed. The comparisons with measured PIE data were also carried out. For the libraries for FBR, the comparisons with the calculations using the old libraries were performed and the effects using different libraries were discussed.
Mori, Takamasa; Nagaya, Yasunobu; Okumura, Keisuke; Kaneko, Kunio*
JAERI-Data/Code 2004-011, 119 Pages, 2004/07
JAERI-Data-Code-2004-011.pdf:5.93MB
The 2nd version of code system, LICEM-2, has been developed to produce neutron cross section libraries for the MVP continuous energy Monte Carlo code from an evaluated nuclear data library in the ENDF format. The code system can process nuclear data in the latest ENDF-6 format and produce cross section libraries for MVP's capability of transport calculation at arbitrary temperature. By using the present system, MVP neutron cross section libraries have been prepared from the latest evaluations of JENDL, ENDF/B and JEFF data bases. This report describes the specification of MVP neutron cross section library, the details of each code in the code system, how to use them and MVP neutron cross section libraries produced with the code system.
Sakurai, Kiyoshi; Kume, Etsuo; Maekawa, Fujio; Nojiri, Ichiro*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(2), p.196 - 201, 2003/06
New attempt on the Monte Carlo seminars is as following; authors prepared the practical lecture note and the text book of continuous energy Monte Carlo method. The exact evaluation method of lower weight bound was proposed in the shielding safety analysis seminar and the high energy calculation seminar. For the general Monte Carlo calculation, the neutron cross-section library including 340 nuclides with 293K, that was compiled from JENDL-3.2, was used for all Monte Carlo Calculation seminars. Also for the check of the calculation method, benchmark experiment problem was used for each calculation seminar.
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
S(n,p)P and 
Cl(n,)P reaction cross sections in the energy range of 13.3-14.9MeV and their integral test below 14MeVY.M.Verzilov*; Maekawa, Fujio; Oyama, Yukio; Ikeda, Yujiro
Fusion Engineering and Design, 37(1), p.95 - 105, 1997/00
Times Cited Count：6 Percentile：47.9(Nuclear Science & Technology)no abstracts in English
Mori, Takamasa; Nakakawa, Masayuki; *
JAERI-Data/Code 96-018, 121 Pages, 1996/05
JAERI-Data-Code-96-018.pdf:3.38MB
no abstracts in English
; Sasa, Toshinobu; Takada, Hiroshi; Takizuka, Takakazu
Proc. of 2nd Int. Conf. on Accelerator-Driven Transmutation Technologies and Applications, 1, p.668 - 674, 1996/00
no abstracts in English
Kosako, Kazuaki*; Yamano, Naoki*; Maekawa, Fujio; Oyama, Yukio
Proc., 1996 Topical Meeting on Radiation Protection and Shielding, 1, p.1088 - 1095, 1996/00
no abstracts in English
Mori, Takamasa; Kosako, Kazuaki*
Purazuma, Kaku Yugo Gakkai-Shi, 71(12), p.1212 - 1219, 1995/12
no abstracts in English
Kosako, Kazuaki*; Maekawa, Fujio; Oyama, Yukio; Uno, Yoshitomo; Maekawa, Hiroshi
JAERI-Data/Code 94-020, 42 Pages, 1994/12
JAERI-Data-Code-94-020.pdf:1.18MB
no abstracts in English
Tanaka, Susumu; Fukuda, Mitsuhiro; Nishimura, Koichi; Yokota, Wataru; Kamiya, Tomihiro; Watanabe, Hiromasa; Yamano, Naoki*; ;
Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.965 - 971, 1994/00
no abstracts in English
Komuro, Yuichi; Okuno, Hiroshi; Naito, Yoshitaka; *; Nagai, Masakatsu*; *; *; *
JAERI-M 93-190, 94 Pages, 1993/10
no abstracts in English
Kosako, Kazuaki*; Oyama, Yukio; Maekawa, Hiroshi
Proc. of the Topical Meeting on New Horizons in Radiation Protection and Shielding, p.357 - 363, 1992/00
no abstracts in English
Kosako, Kazuaki*; Oyama, Yukio; Maekawa, Hiroshi
JAERI-M 91-187, 120 Pages, 1991/11
no abstracts in English
Komuro, Yuichi; Okuno, Hiroshi; Naito, Yoshitaka; *; *; *
JAERI-M 90-126, 125 Pages, 1990/08
no abstracts in English
Nakakawa, Masayuki; Mori, Takamasa; *
JAERI-M 90-097, 95 Pages, 1990/06
no abstracts in English
Masukawa, Fumihiro; Nakagawa, Tsuneo; Iijima, Shungo*
Journal of Nuclear Science and Technology, 27(6), p.572 - 576, 1990/06
no abstracts in English
Kosako, Kazuaki*; Oyama, Yukio; Maekawa, Hiroshi; Nakamura, Tomoo
JAERI-M 88-076, 71 Pages, 1988/03
no abstracts in English
Nakagawa, Masayuki;
JAERI-M 84-126, 74 Pages, 1984/07
no abstracts in English
