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Journal Articles

Passively safe small reactor for distributed energy system, PSRD

Ochiai, Masaaki

Nihon Genshiryoku Gakkai-Shi, 43(11), p.1070 - 1074, 2001/11

no abstracts in English

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.

JAEA Reports

Development of a position-sensitive fission counter and measurement of neutron flux distributions

Yamagishi, Hideshi; Soyama, Kazuhiko; Kakuta, Tsunemi; Ochiai, Masaaki; Iwamura, Takamichi; Saishu, Sadanori*; Urakami, Masao*; Masuda, Naohiro*; Yamauchi, Yuki*; Otani, Junichi*; et al.

JAERI-Tech 2001-053, 19 Pages, 2001/08

JAERI-Tech-2001-053.pdf:2.48MB

no abstracts in English

Journal Articles

Development of in-vessel type control rod drive mechanism for marine reactor

Ishida, Toshihisa; Imayoshi, Sho*; Yoritsune, Tsutomu; Nunokaya, Hiroshi*; Ochiai, Masaaki; Ishizaka, Yuichi*

Journal of Nuclear Science and Technology, 38(7), p.557 - 570, 2001/07

 Times Cited Count:16 Percentile:74.89(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of ball bearing in high temperature water for in-vessel type control rod drive mechanism of advanced marine reactor

Nunokawa, Hiroshi*; Yoritsune, Tsutomu; Imayoshi, Sho*; Kasahara, Yoshiyuki*; Ochiai, Masaaki; Ishida, Toshihisa

JAERI-Tech 2001-040, 115 Pages, 2001/06

JAERI-Tech-2001-040.pdf:10.18MB

no abstracts in English

JAEA Reports

Feasibility study on floating nuclear power plant, 2; Safety design study of FNPP (Contract research)

Yabuuchi, Noriaki; Takahashi, Masao*; Nakazawa, Toshio; Sato, Kazuo*; Shimazaki, Junya; Ochiai, Masaaki

JAERI-Research 2000-064, 76 Pages, 2001/02

JAERI-Research-2000-064.pdf:5.88MB

no abstracts in English

JAEA Reports

Feasibility study on floating nuclear power plant, 1; Conceptual design study of FNPP (Contract research)

Yabuuchi, Noriaki; Takahashi, Masao*; Nakazawa, Toshio; Sato, Kazuo*; Shimazaki, Junya; Ochiai, Masaaki

JAERI-Research 2000-063, 69 Pages, 2001/02

JAERI-Research-2000-063.pdf:4.41MB

no abstracts in English

Journal Articles

Activities of design studies on innovative small and medium LWRs in JAERI

Iwamura, Takamichi; Ochiai, Masaaki

Proceedings of 1st Asian Specialist Meeting of Future Small-Sized LWR Development, p.7_1 - 7_9, 2001/00

JAERI has developed two types of small and medium size Light Water Reactors to meet the goals of innovative nuclear reactors such as sustainability and diversification of energy utilization. One is the Reduced-Moderation light Water Reactor (RMWR) with passive safety features. The reactor core consists of MOX fuel assemblies with tight lattice arrangement to increase the conversion ratio by reducing the moderation of neutron energy. The core design of 330MWe output with the operational cycle of 26 months was accomplished. A breeding ratio of 1.01, negative void coefficient and natural circulation cooling of the core were realized under the discharged burn-up of 60GWd/t. The other is the Passive Safe small Reactor for Distributed energy systems (PSRD) to diversify the nuclear energy utilization. An innovative advanced marine reactor (MRX) is used to supply the small grid electricity or electricity and heat co-supply by installing it on a barge. A small integral LWR for underground deployment is also studied for exclusive use of heat supply to household or office.

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

Passively safe small reactor at energy consumption area

Ochiai, Masaaki

Enerugi, 33(10), p.49 - 53, 2000/10

no abstracts in English

JAEA Reports

Building of nuclear ship engineering simulation system; Development of the simulator for the integral type reactor

Takahashi, Teruo; Shimazaki, Junya; Nakazawa, Toshio; Yabuuchi, Noriaki; Fukuhara, Yoshifumi*; Kusunoki, Tsuyoshi; Ochiai, Masaaki

JAERI-Tech 2000-039, p.94 - 0, 2000/03

JAERI-Tech-2000-039.pdf:4.0MB

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

JAEA Reports

Workshop summary report on the advanced utilization of plutonium in water cooled reactor; March 2nd, 1999, in Tokyo

Nakajima, Nobuya; Ochiai, Masaaki

JAERI-Conf 99-014, p.218 - 0, 1999/12

JAERI-Conf-99-014.pdf:11.65MB

no abstracts in English

JAEA Reports

Study on nuclear physics of high burnup full MOX PWR core

Kugo, Teruhiko; Shimada, Shoichiro*; Okubo, Tsutomu; Ochiai, Masaaki

JAERI-Research 98-059, 40 Pages, 1998/10

JAERI-Research-98-059.pdf:1.73MB

no abstracts in English

Journal Articles

Conceptual designing of water-cooled reactors with increased or reduced moderation

Okubo, Tsutomu; Kugo, Teruhiko; *; Shimada, Shoichiro*; Ochiai, Masaaki

Proc. of Workshop on Advanced Reactors with Innovative Fuels, p.127 - 137, 1998/10

no abstracts in English

JAEA Reports

The Study Meeting Report on the Undermoderated Spectrum Reactor; March4-5, 1998, JAERI, Tokai Japan

; Ochiai, Masaaki

JAERI-Conf 98-013, 279 Pages, 1998/09

JAERI-Conf-98-013.pdf:11.39MB

no abstracts in English

JAEA Reports

Study on nuclear physics of high burn-up full MOX-BWR core

*; Okubo, Tsutomu; Ochiai, Masaaki

JAERI-Research 98-047, 46 Pages, 1998/08

JAERI-Research-98-047.pdf:1.79MB

no abstracts in English

JAEA Reports

Steady-state and transient DNB analyses for JAERI passive safety reactor (JPSR) using COBRA-IV-I and RETRAN-02/Mod3 codes

Okubo, Tsutomu; X.Jiang*; Araya, Fumimasa; Ochiai, Masaaki

JAERI-Research 98-042, 49 Pages, 1998/08

JAERI-Research-98-042.pdf:1.58MB

no abstracts in English

24 (Records 1-20 displayed on this page)