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JAEA Reports

Behavior of the regulating control rod on automatic power control mode in operation of JMTR

Nagao, Yoshiharu; Miyazawa, Masataka; Komukai, Bunsaku; Fujiki, Kazuo

JAERI-Tech 2003-067, 33 Pages, 2003/07

JAERI-Tech-2003-067.pdf:1.63MB

no abstracts in English

JAEA Reports

Thermal hydraulic analysis of the JMTR improved LEU-core

Tabata, Toshio; Nagao, Yoshiharu; Komukai, Bunsaku; Naka, Michihiro; Takeda, Takashi*; Fujiki, Kazuo

JAERI-Tech 2002-100, 108 Pages, 2003/01

JAERI-Tech-2002-100.pdf:4.44MB

After the investigation of the new core arrangement for the JMTR reactor in order to enhance the fuel burn-up and consequently extend the operation period, the "improved LEU core" that utilized 2 additional fuel elements instead of formerly installed reflector elements, was adopted. This report describes the results of the thermal-hydraulic analysis of the improved LEU core as a part of safety analysis for the licensing. The analysis covers steady state, abnormal operational transients and accidents, which were described in the annexes of the licensing documents as design bases events. Calculation conditions for the computer codes were conservatively determined based on the neutronic analysis results and others. The results of the analysis, that revealed the safety criteria were satisfied on the fuel temperature, DNBR and primary coolant temperature, were used in the licensing. The operation license of the JMTR with the improved LEU core was granted in March 2001, and the reactor operation with new core started in November 2001 as 142nd operation cycle.

JAEA Reports

Published literature on the research activities using the JMTR, 2; Publication as JAERI research reports

Nagao, Yoshiharu; Ishii, Tadahiko; Niimi, Motoji; Fujiki, Kazuo; Takahashi, Hidetake

JAERI-Review 2002-031, 119 Pages, 2002/11

JAERI-Review-2002-031.pdf:5.64MB

The published reports on the research and development activities using the JMTR since 1971 to date have been surveyed by the search of literature database and questionnaire survey. This report compiles the title lists and abstracts of reports published by JAERI and survey the trend of the research and development in JAERI using JMTR.

JAEA Reports

Neutronics analysis of the improved LEU core in JMTR

Komukai, Bunsaku; Naka, Michihiro; Tabata, Toshio; Nagao, Yoshiharu; Takeda, Takashi*; Fujiki, Kazuo

JAERI-Tech 2002-067, 75 Pages, 2002/08

JAERI-Tech-2002-067.pdf:3.41MB

no abstracts in English

JAEA Reports

Published literature on the research activities using the JMTR

Nagao, Yoshiharu; Ishii, Tadahiko; Takeda, Takashi; Fujiki, Kazuo

JAERI-Review 2002-007, 191 Pages, 2002/03

JAERI-Review-2002-007.pdf:10.97MB

The published reports on the research activities using the JMTR since 1971 to date have been surveyed by the search of literature database and questionnaire survey. This report summarized the result of survey as the title lists by research categories.

Journal Articles

Current status and future prospects of JMTR Hot Laboratory

Saito, Junichi; Ishii, Toshimitsu; Omi, Masao; Fujiki, Kazuo; Ito, Haruhiko; Takahashi, Hidetake

KAERI/GP-192/2002, p.3 - 11, 2002/00

no abstracts in English

Journal Articles

Evaluation of neutron flux and gamma heating for irradiation tests of JMTR

Nagao, Yoshiharu; Itabashi, Yukio; Komori, Yoshihiro; Niimi, Motoji; Fujiki, Kazuo

KAERI/GP-195/2002, p.49 - 55, 2002/00

An improved analysis procedure has been introduced to evaluate irradiation field at each specimen in the irradiation capsule by using the MCNP code, which is able to model the complicated structure of the capsule directly. As the verification results, it was confirmed that the calculated fast and thermal neutron flux/fluence were agreed with measured ones within $$pm$$10% and $$pm$$30%, respectively, for the irradiation tests in the JMTR. Concerning gamma dose/spectrum, it was confirmed that the calculated temperature was evaluated within -3$$sim$$+14% using gamma heating obtained by MCNP calculations. The evaluations of neutron flux/fluence and specimens temperature with high accuracy are therefore possible in the irradiation test of the JMTR.

Journal Articles

Characterization of neutron field for stainless steel irradiation experiments in JMTR

Shimakawa, Satoshi; Nagao, Yoshiharu; Fujiki, Kazuo

Reactor Dosimetry: Radiation Metrology and Assessment (ASTM STP 1398), p.244 - 251, 2001/00

no abstracts in English

Journal Articles

The 6th Asian Symposium on Research Reactors (ASRR-VI)

Fujiki, Kazuo

Nihon Genshiryoku Gakkai-Shi, 41(9), p.933 - 934, 1999/09

no abstracts in English

JAEA Reports

Evaluation of neutronic characteristic of irradiation field in MEU6-core; Comparison of neutron flux and neutron spectrum in MEU6-core and mixed-core

Nagao, Yoshiharu; Komukai, Bunsaku; Tabata, Toshio; Takeda, Takashi; Fujiki, Kazuo

JAERI-Tech 99-063, 57 Pages, 1999/08

JAERI-Tech-99-063.pdf:2.78MB

no abstracts in English

JAEA Reports

Safety analysis of JMTR core with 6-MEU fuel elements and 16-LEU fuel elements

Tabata, Toshio; Komukai, Bunsaku; Nagao, Yoshiharu; Shimakawa, Satoshi; Koike, Sumio; Takeda, Takashi; Fujiki, Kazuo

JAERI-Tech 99-021, 68 Pages, 1999/03

JAERI-Tech-99-021.pdf:2.6MB

no abstracts in English

Journal Articles

Application of plasma-induction-hybrid melter to the research on volume reduction and stabilization of low level radioactive solid waste

Hirabayashi, Takakuni; Kanazawa, Katsuo; Fujiki, Kazuo; *; *

Proc. of Int. Conf. on Incineration & Thermal Treatment Technologies (IT3 Conference), p.261 - 264, 1998/00

no abstracts in English

Journal Articles

Decommissioning of the critical facility JMTRC

Takeda, Takashi; Komukai, Bunsaku; ; ; Fujiki, Kazuo; Ooka, Norikazu

Dekomisshoningu Giho, (17), p.55 - 62, 1997/12

no abstracts in English

Journal Articles

Melting tests for recycling slightly radioactive metallic wastes arising from decommissioning

Nakamura, Hisashi; Fujiki, Kazuo

Nuclear Technology, 117(2), p.195 - 205, 1997/02

 Times Cited Count:8 Percentile:56.36(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Radionuclide transport behavior during melting and ingot making of ferrous waste

*; Nakamura, Hisashi; Kanazawa, Katsuo; Fujiki, Kazuo; *

Chuzo Kogaku, 68(8), p.644 - 649, 1996/00

no abstracts in English

Journal Articles

Application of exemption principle and recycling for the reduction of radioactive waste

Fujiki, Kazuo; Nakamura, Hisashi

Doryoku, Enerugi Gijutsu No Saizensen : Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu 1996, 0, p.372 - 374, 1996/00

no abstracts in English

Journal Articles

Results and outline of JPDR dismantling demonstration project

Miyasaka, Yasuhiko; ; Tanaka, Mitsugu; Nakamura, Hisashi; ; Tachibana, Mitsuo; ; Hatakeyama, Mutsuo; ; Yoshimori, Michiro; et al.

Nihon Genshiryoku Gakkai-Shi, 38(7), p.553 - 576, 1996/00

no abstracts in English

Journal Articles

R&D on melting of radioactive metal wastes at JAERI

Nakamura, Hisashi; Kanazawa, Katsuo; Fujiki, Kazuo

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 4, 0, p.1785 - 1789, 1995/00

no abstracts in English

Journal Articles

Progress with tests on melting of low-level metallic waste at JAERI

Fujiki, Kazuo;

EUR-15691, 0, p.133 - 146, 1994/00

no abstracts in English

Journal Articles

Considerations on the recycling of low-level waste in Japan

Fujiki, Kazuo;

EUR-15691, 0, p.397 - 403, 1994/00

no abstracts in English

45 (Records 1-20 displayed on this page)