Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 42

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Investigation on high availability-factor achievement of JMTR; How to achieve 60% availability-factor

Takemoto, Noriyuki; Izumo, Hironobu; Inoue, Shuichi; Abe, Shinichi; Naka, Michihiro; Akashi, Kazutomo; Omi, Masao; Miyazawa, Masataka; Baba, Osamu*; Nagao, Yoshiharu

JAEA-Review 2008-051, 36 Pages, 2008/10

JAEA-Review-2008-051.pdf:3.14MB

The JMTR has been refurbished to restart operation in FY2011. The restarted JMTR plays roles of (1) measures for long-term operation of light water reactors, (2) improvement in scientific technique, (3) increase of industrial use, (4) training of human resources, etc. It is needed to operate the restarted JMTR safety and stably and maintain high available factor (50$$sim$$70%) because of increasing of irradiation utilization demand. In this report, measures for training of reactor operators, organization for operating, etc were proposed to operate reactor safety and smoothly. And also reactor operation procedure was examined to improve available factor up to world level for materials testing reactor. As a result, it was turned out to be possible to realize stably 210 days operation per year (available factor: 60%).

JAEA Reports

The Approaches of safety design and safety evaluation at HTTR (High Temperature Engineering Test Reactor)

Iigaki, Kazuhiko; Saikusa, Akio; Sawahata, Hiroaki; Shinozaki, Masayuki; Tochio, Daisuke; Homma, Fumitaka; Tachibana, Yukio; Iyoku, Tatsuo; Kawasaki, Kozo; Baba, Osamu*

JAEA-Review 2006-010, 90 Pages, 2006/07

JAEA-Review-2006-010.pdf:5.65MB

Gas Cooled Reactor has long history of nuclear development, and High Temperature Gas Cooled Reactor (HTGR) has been expected that it can be supply high temperature energy to chemical industry and to power generation from the points of view of the safety, the efficiency, the environment and the economy. The HTGR design is tried to installed passive safety equipment. The current licensing review guideline was made for a Low Water Reactor (LWR) on safety evaluation therefore if it would be directly utilized in the HTGR it needs the special consideration for the HTGR. This paper describes that investigation result of the safety design and the safety evaluation traditions for the HTGR, comparison the safety design and safety evaluation feature for the HTGT with it's the LWR, and reflection for next HTGR based on HTTR operational experiment.

Journal Articles

Highly polarized electrons from GaAs-GaAsP and InGaAs-AlGaAs strained-layer superlattice photocathodes

Nishitani, Tomohiro; Nakanishi, Tsutomu*; Yamamoto, Masahiro*; Okumi, Shoji*; Furuta, Fumio*; Miyamoto, Masaharu*; Kuwahara, Makoto*; Yamamoto, Naoto*; Naniwa, Kenichi*; Watanabe, Osamu*; et al.

Journal of Applied Physics, 97(9), p.094907_1 - 094907_6, 2005/05

 Times Cited Count:64 Percentile:87.31(Physics, Applied)

no abstracts in English

JAEA Reports

Evaluations of heavy nuclide data for JENDL-3.3

Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.

JAERI-Research 2003-026, 53 Pages, 2003/12

JAERI-Research-2003-026.pdf:2.48MB

New evaluations of neutron nuclear data for Uranium, Plutonium, and Thorium isotopes which are essential for applications to nuclear technology were carried out for the Japanese Evaluated Nuclear Data Library, JENDL-3.3. The objectives of the current release of JENDL were to fix several problems which have been reported for the previous version, to improve the accuracy of the data, and to evaluate covariances for the important nuclides. Quantities in JENDL-3.2 were extensively re-evaluated or replaced by more reliable values. The heavy nuclide data in JENDL-3.3 were validated with several benchmark tests, and it was reported that the current release gave a good prediction of criticalities.

Journal Articles

Japanese evaluated nuclear data library version 3 revision-3; JENDL-3.3

Shibata, Keiichi; Kawano, Toshihiko*; Nakagawa, Tsuneo; Iwamoto, Osamu; Katakura, Junichi; Fukahori, Tokio; Chiba, Satoshi; Hasegawa, Akira; Murata, Toru*; Matsunobu, Hiroyuki*; et al.

Journal of Nuclear Science and Technology, 39(11), p.1125 - 1136, 2002/11

 Times Cited Count:669 Percentile:96.97(Nuclear Science & Technology)

Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for $$^{235}$$U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.

Journal Articles

JAERI acquired a certificate of the pre-operation test for the High Temperature Engineering Test Reactor (HTTR)

Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Okubo, Minoru; Baba, Osamu

Nihon Genshiryoku Gakkai-Shi, 44(4), P. 310, 2002/04

no abstracts in English

Journal Articles

High Temperature Engineering Test Reactor (HTTR) of JAERI attained the maximum reactor thermal power of 30MW

Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Okubo, Minoru; Baba, Osamu

Nihon Genshiryoku Gakkai-Shi, 44(1), P. 2, 2002/01

no abstracts in English

JAEA Reports

Earthquake observation database in JAERI Oarai site obtained by vertical instrument arrays from 1987-2000

Ebisawa, Katsumi; Yamada, Hiroyuki; Tsutsumi, Hideaki*; Shibata, Katsuyuki; Ando, Kazuhiro*; Baba, Osamu; Suzuki, Hideyuki

JAERI-Data/Code 2001-009, 96 Pages, 2001/03

JAERI-Data-Code-2001-009.pdf:4.14MB

no abstracts in English

Journal Articles

Simultaneous evaluation of fission cross sections of uranium and plutonium isotopes for JENDL-3.3

Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.

Journal of Nuclear Science and Technology, 37(4), p.327 - 334, 2000/04

no abstracts in English

JAEA Reports

Evaluation of fission cross sections and covariances for $$^{233}$$U,$$^{235}$$U,$$^{238}$$U,$$^{239}$$Pu,$$^{240}$$Pu,and $$^{241}$$Pu

Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.

JAERI-Research 2000-004, p.76 - 0, 2000/02

JAERI-Research-2000-004.pdf:2.39MB

no abstracts in English

Journal Articles

Present status and future perspective of research and test reactors in JAERI

Kaieda, Keisuke; Baba, Osamu

Proceedings of 7th Meeting of the International Group on Research Reactors (IGORR-7) (CD-ROM), p.7 - 0, 1999/00

no abstracts in English

Journal Articles

Application of thermography as a technique for nondestructive evaluation on nuclear facilities

Naka, Michihiro; ; Ooka, Norikazu; ; Ito, Haruhiko; Baba, Osamu

Proc. of CORENDE, 3 Pages, 1997/00

no abstracts in English

Journal Articles

Construction of the HTTR and its testing program

Tanaka, Toshiyuki; Baba, Osamu; ; Shiozawa, Shusaku; Okubo, Minoru

10th Pacific Basin Nuclear Conf. (10-PBNC), 1, p.811 - 818, 1996/10

no abstracts in English

Journal Articles

Construction of the HTTR and its testing program

Tanaka, Toshiyuki; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru;

JAERI-Conf 96-010, 0, p.97 - 104, 1996/07

no abstracts in English

Journal Articles

Status of reduced enrichment program for research reactors in Japan

Kanda, Keiji*; *; Isshiki, Masahiko; Baba, Osamu; Tsuruta, Harumichi

1996 Int. Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), 0, 8 Pages, 1996/00

no abstracts in English

Journal Articles

Safety concept of severe accident free HTR and its demonstration by the HTTR

Kunitomi, Kazuhiko; Shiozawa, Shusaku; Baba, Osamu

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 2, p.303 - 307, 1996/00

no abstracts in English

Journal Articles

Design and present status of high-temperature engineering test reactor

Baba, Osamu; Kunitomi, Kazuhiko; Kawaji, Satoshi; Tanaka, Toshiyuki; Shiozawa, Shusaku; Okubo, Minoru

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 2, p.281 - 287, 1996/00

no abstracts in English

Journal Articles

High-temperature engineering test reactor (HTTR)

Baba, Osamu

Sci. Technol. Jpn., 15(58), p.7 - 9, 1996/00

no abstracts in English

Journal Articles

Characteristics of earthquake ground motion with vertical instrument arroys on hard rock

; Baba, Osamu; Suzuki, Hideyuki; *; *; *

Dai-23-Kai Jishin Kogaku Kenkyu Happyokai Koen Gaiyoshu, 0, p.53 - 56, 1995/00

no abstracts in English

Journal Articles

Present status and prospects of high-temperature engineering test reactor (HTTR) program

Tanaka, Toshiyuki; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru; Tobioka, Toshiaki

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Enginering (ICONE), Vol. 2, 0, p.745 - 750, 1995/00

no abstracts in English

42 (Records 1-20 displayed on this page)