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Journal Articles

Research activities of Japan Nuclear Data Committee in fiscal years of 2003 and 2004

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.

Journal Articles

Nuclear data evaluations for JENDL high-energy file

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 (${it n, p, d, t,}$ $$^{3}$$He, $$alpha$$, and $$pi$$) and $$gamma$$-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.

Journal Articles

Research activities of Japanese Nuclear Data Committee in the fiscal years of 2001 and 2002

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

JAEA Reports

JENDL Dosimetry File 99 (JENDL/D-99)

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

JAERI-1344.pdf:7.59MB

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.

JAEA Reports

Neutronic study of a very small reactor MR-1G core for exclusive use of heat supply

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 $$^{235}$$U enrichment of UO$$_{2}$$ fuel rods were surveyed as design parameters. The $$^{235}$$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.

Journal Articles

Estimates of collective doses from a hypothetical accident of a nuclear submarine

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:20.38(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.

JAEA Reports

Study on operation conditions and an operation system of a nuclear powered submersible research vessel; Report of working group on application of a very small nuclear reactor to an ocean research

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.

JAEA Reports

Concept of a nuclear powered submersible research vessel and a compact reactor

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.

JAEA Reports

Neutronic study of SCR core for under-sea scientific research vessel

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, $$^{235}$$U enrichment of UO$$_{2}$$ fuel rods and reflector materials were surveyed. The $$^{235}$$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.

JAEA Reports

Comparison of (n,2n) and (n,3n) reaction cross sections for fission products in JENDL-3.2 with available experimental and other evaluated cross section data

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.

JAEA Reports

Consistent evaluations of (n,2n) and (n,np) reaction excitation functions for some even-even isotopes using empirical systematics

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

JAEA Reports

Neutronic study of DRX (Deep Sea Reactor X) core for deep sea research vessel

Odano, Naoteru; Ishida, Toshihisa

JAERI-Research 2001-004, 36 Pages, 2001/03

JAERI-Research-2001-004.pdf:1.51MB

no abstracts in English

Journal Articles

Design study of a district-heating reactor installed in the basement of building

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:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Design of advanced integral-type marine reactor, MRX

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:39 Percentile:90.63(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of buildup of activated corrosion products for highly compact marine reactor DRX without primary coolant water purification system

Odano, Naoteru; Ishida, Toshihisa

Journal of Nuclear Science and Technology, 37(Suppl.1), p.584 - 588, 2000/03

no abstracts in English

Journal Articles

Shielding design for steam generator of advanced integral marine reactor MRX

Odano, Naoteru; Yamaji, Akio*; Ishida, Toshihisa

Journal of Nuclear Science and Technology, 37(Suppl.1), p.78 - 82, 2000/03

no abstracts in English

Journal Articles

Submersible compact reactor SCR for under-sea research vessel

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

Journal Articles

Advanced marine reactor MRX and application to nuclear barge supplying electricity and heat

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

Journal Articles

Research and development on very small reactor for heat supply

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

Journal Articles

A Nuclear reactor installed in the basement of a building for heat supply

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

22 (Records 1-20 displayed on this page)