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Igashira, Masayuki*; Watanabe, Yukinobu*; Fukahori, Tokio; Okumura, Keisuke; Katakura, Junichi; Chiba, Satoshi; Shibata, Keiichi; Yamano, Naoki*; Nakagawa, Tsuneo; Odano, Naoteru*; et al.
Nihon Genshiryoku Gakkai Wabun Rombunshi, 6(1), p.85 - 96, 2007/03
This technical note summarizes research activities on nuclear data carried out by Japanese Nuclear Data Committee (JNDC) during the fiscal years of 2003 and 2004. During this period, the nuclear data files for special purposes (JENDL-HE-2004 and JENDL-PD-2004) were released. Other activities are described: analysis of post nuclear fuel irradiation experiments, nuclear chart and nuclear data evaluation for astrophysics.
Watanabe, Yukinobu*; Fukahori, Tokio; Kosako, Kazuaki*; Shigyo, Nobuhiro*; Murata, Toru*; Yamano, Naoki*; Hino, Tetsushi*; Maki, Koichi*; Nakashima, Hiroshi; Odano, Naoteru*; et al.
AIP Conference Proceedings 769, p.326 - 331, 2005/05
An overview is presented of recent nuclear data evaluations performed for the JENDL high-energy (JENDL-HE) file, in which neutron and proton cross sections for energies up to 3 GeV are included for the whole 132 nuclides. The current version of the JENDL-HE file consists of neutron total cross sections, nucleon elastic scattering cross sections and angular distributions, nonelastic cross sections, production cross sections and double-differential cross sections of secondary light particles (
He, 
, and 
) and 
-rays, isotope production cross sections, and fission cross sections in the ENDF6 format. The present evaluations are performed on the basis of experimental data and theoretical model calculations. For the cross section calculations, we have constructed a hybrid calculation code system with some available nuclear model codes and systematics-based codes, such as ECIS96, OPTMAN, GNASH, JQMD, JAM, TOTELA, FISCAL, and so on. The evaluated cross sections are compared with available experimental data and the other evaluations. Future plans of our JENDL-HE project are discussed along with prospective needs of high-energy cross section data.
Igashira, Masayuki*; Shibata, Keiichi; Takano, Hideki*; Yamano, Naoki*; Matsunobu, Hiroyuki*; Kitao, Kensuke*; Katakura, Junichi; Nakagawa, Tsuneo; Hasegawa, Akira; Iwasaki, Tomohiko*; et al.
Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(1), p.128 - 139, 2004/03
no abstracts in English
Kobayashi, Katsuhei*; Iguchi, Tetsuo*; Iwasaki, Shin*; Aoyama, Takafumi*; Shimakawa, Satoshi; Ikeda, Yujiro; Odano, Naoteru; Sakurai, Kiyoshi; Shibata, Keiichi; Nakagawa, Tsuneo; et al.
JAERI 1344, 133 Pages, 2002/01
The JENDL Dosimetry File 99 (JENDL/D-99) has been prepared for determinations of neutron flux/fluence and energy spectrum at specific neutron fields. This file contains data for 67 reactions with 47 nuclides. Cross sections for 33 major dosimetry reactions and their covariance data were simultaneously generated and the other 34 reaction data were mainly adopted from the first version, JENDL/D-91. The GMA code was mainly used for most of the evaluation procedures by referring the basic experimental data in EXFOR. The resultant data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-6 format. In order to confirm reliability of the data, several integral tests have been carried out: comparison with the data in IRDF-90V2 and average cross sections measured in fission neutron fields, fast/thermal reactor spectra, DT neutron fields and Li(d,n) neutron fields. The contents of JENDL/D-99 and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form in the Appendix.
Odano, Naoteru; Ishida, Toshihisa; Ochiai, Masaaki
JAERI-Research 2001-044, 53 Pages, 2001/10
JAERI-Research-2001-044.pdf:2.35MB
A very small reactor, MR-1G with a thermal output of 1 MW, is the integral-pressurized type reactor to be used for heat supply to an office building in a city. Neutronic study has been carried out for design of the MR-1G, the core of which could achieve continuous long-term operation without refueling for 10 years assuming a load factor of the core of 44 %. In the present study, arrangement of fuel rods and 
U enrichment of UO
fuel rods were surveyed as design parameters. The U enrichment was determined to be 8.5 wt% to satisfy design requirement. Reactor physics parameters including reactivity coefficients and power distributions were evaluated for the determined core specifications. Reactor physics parameters related to core safety were also analyzed. Results of the safety analysis indicated that the determined core specifications satisfied design conditions. Reactor shutdown performance by dropping the reflector, which was adopted as a passive reactor shutdown system, was analyzed and confirmed it's availability from a viewpoint of reactor physics.
Kobayashi, Takuya; Togawa, Orihiko; Odano, Naoteru; Ishida, Toshihisa
Journal of Nuclear Science and Technology, 38(8), p.658 - 663, 2001/08
Times Cited Count：2 Percentile：19.28(Nuclear Science & Technology)The collective dose to the Japanese population has been estimated from a hypothetical accident of a nuclear submarine if it sinks in an offshore region around Japan. A computer code system DSOCEAN has been used for assessing the collective dose due to radionuclides released to the ocean from a sunken nuclear submarine. The maximum of the estimated collective effective dose equivalent by the annual intake of marine products after radionuclide releases for one year is approximately 0.5% of the annual average dose by the natural radiation that is reported by UNSCEAR.
Ura, Tamaki*; Takamasa, Tomoji*; Nishimura, Hajime*; Aoki, Taro*; Ueno, Michio*; Maeda, Toshio*; Nakamura, Masato*; Shimazu, Shunsuke*; Tokunaga, Sango*; Shibata, Yozo*; et al.
JAERI-Tech 2001-049, 154 Pages, 2001/07
JAERI-Tech-2001-049.pdf:11.24MB
JAERI has studied on design and operation of a nuclear powered submersible research vessel, which will navigate under sea in the Arctic Ocean, as a part of the design study of advanced marine reactors. This report describes operation conditions and an operating system of the vessel those were discussed by the specialists of hull design, sound positioning, ship motions and oceanography, etc. The design conditions on ship motions for submersible vessels were surveyed considering regulations in our country, and ship motions were evaluated assuming the observation activities in the Arctic Ocean. A submarine transponder system and an on ice communication buoy system were examined as a positioning and communication system supposing the activity under ice. Procedures to secure safety of nuclear powered submersible research vessel were discussed based on the investigation of accidents. These results were reflected to the concept of the nuclear powered submersible research vessel, and subjects fto be settled in the next step were clarified.
Kusunoki, Tsuyoshi; Takahashi, Teruo*; Nishimura, Hajime*; Tokunaga, Sango*; Odano, Naoteru; Yoritsune, Tsutomu; Ishida, Toshihisa
JAERI-Tech 2001-045, 68 Pages, 2001/07
JAERI-Tech-2001-045.pdf:5.33MB
A concept of a submersible research vessel navigating in 600 m depth and a compact nuclear reactor were carried out for the expansion of the nuclear power utilization. The mission of the vessel is the research of mechanism of the climate change. Through conditions of the Arctic Ocean and the sea at high latitude have significant impacts on the global environmental change, it is difficult to investigate those areas by ordinary ships because of thick ice or storm. By taking account of the research mission, the basic specifications of the vessel are decided; the total weight is 500 t, the submersible depth is 600 m, the maximum speed is 12 knots (22.2km/h), and the number of crews is 16. Nuclear power has an advantage in supplying large power of electricity in the sea for long period. Based on the requirements, it has been decided that two sets of compact nuclear reactor, SCR, which is light-weighted and of enhanced safety characteristics to supply the total electricity of 500 kW.
Odano, Naoteru; Ishida, Toshihisa; Wada, Koji*; Imai, Hiroshi*
JAERI-Research 2001-039, 59 Pages, 2001/07
JAERI-Research-2001-039.pdf:4.47MB
A very small reactor, SCR (Submersible Compact Reactor), whose thermal output is 1250 kW, is an integral-pressurized type reactor to be used as a power source for a scientific research vessel in medium depth region of the Arctic Ocean. Neutronic study has been carried out for design of the SCR core of which could achieve continuous long-term operation without refueling for 10 years considering 50 % of load factor of the core. In the present study, arrangement of fuel rods, U enrichment of UO fuel rods and reflector materials were surveyed. The U enrichment has been determined to be 9.5 wt% to satisfy design criteria. In the present study Be metal was adopted as a reflector material. Reactor physics parameters including reactivity coefficients and power distributions were evaluated for the determined core specifications. Reactor physics parameters related to core safety were also confirmed and the evaluated parameters indicated that the determined core specifications in this study satisfied design conditions.
Manokhin, V. N.*; Odano, Naoteru; Hasegawa, Akira
JAERI-Data/Code 2001-019, 169 Pages, 2001/07
JAERI-Data-Code-2001-019.pdf:5.26MB
Results of comparison of (n,2n) and (n,3n) reaction cross sections for 155 nuclei (Ge - Tb) in JENDL-3.2 with available experimental data, various evaluated data, and those estimated from systematics are summarized to assess validity of cross sections for threshold reactions for fission product nuclei in JENDL-3.2. Plots for comparisons are compiled and issues in cross section data in JENDL-3.2 are also discussed.
Manokhin, V. N.*; Odano, Naoteru; Hasegawa, Akira
JAERI-Research 2001-013, 22 Pages, 2001/03
JAERI-Research-2001-013.pdf:1.46MB
no abstracts in English
Odano, Naoteru; Ishida, Toshihisa
JAERI-Research 2001-004, 36 Pages, 2001/03
JAERI-Research-2001-004.pdf:1.51MB
no abstracts in English
Kusunoki, Tsuyoshi; Odano, Naoteru; Nakajima, Nobuya; Fukuhara, Yoshifumi*; Ochiai, Masaaki
Nihon Genshiryoku Gakkai-Shi, 42(11), p.1195 - 1203, 2000/11
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)no abstracts in English
Kusunoki, Tsuyoshi; Odano, Naoteru; Yoritsune, Tsutomu; Ishida, Toshihisa; Hoshi, Tsutao*; Sako, Kiyoshi*
Nuclear Engineering and Design, 201(2-3), p.155 - 175, 2000/10
Times Cited Count：51 Percentile：93.22(Nuclear Science & Technology)no abstracts in English
Odano, Naoteru; Yamaji, Akio*; Ishida, Toshihisa
Journal of Nuclear Science and Technology, 37(Suppl.1), p.78 - 82, 2000/03
no abstracts in English
Odano, Naoteru; Ishida, Toshihisa
Journal of Nuclear Science and Technology, 37(Suppl.1), p.584 - 588, 2000/03
no abstracts in English
Ishida, Toshihisa; Kusunoki, Tsuyoshi; Odano, Naoteru; Yoritsune, Tsutomu; Fukuhara, Yoshifumi*; Ochiai, Masaaki; Hoshi, Tsutao*
Proceedings of International Workshop on Utilization of Nuclear Power in Oceans (N'ocean 2000), p.55 - 66, 2000/02
no abstracts in English
Odano, Naoteru; Kusunoki, Tsuyoshi; Yoritsune, Tsutomu; Fukuhara, Yoshifumi*; Saito, Kazuo*; Takahashi, Teruo*; Ishida, Toshihisa
Proceedings of International Workshop on Utilization of Nuclear Power in Oceans (N'ocean 2000), p.164 - 169, 2000/02
no abstracts in English
Nakajima, Nobuya; Kusunoki, Tsuyoshi; Odano, Naoteru; Ochiai, Masaaki
Dai-7-Kai Doryoku Enerugi Gijutsu Shimpojiumu Koen Rombunshu (00-11), p.225 - 228, 2000/00
no abstracts in English
Kusunoki, Tsuyoshi; Odano, Naoteru; Yoritsune, Tsutomu; Fukuhara, Yoshifumi*; Nakajima, Nobuya; Ochiai, Masaaki
Proceedings of the 4th JSME-KSME Thermal Engineering Conference, p.1_61 - 1_66, 2000/00
no abstracts in English
