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Journal Articles

Conceptual study of a plutonium burner high temperature gas-cooled reactor with high nuclear proliferation resistance

Goto, Minoru; Demachi, Kazuyuki*; Ueta, Shohei; Nakano, Masaaki*; Honda, Masaki*; Tachibana, Yukio; Inaba, Yoshitomo; Aihara, Jun; Fukaya, Yuji; Tsuji, Nobumasa*; et al.

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.507 - 513, 2015/09

A concept of a plutonium burner HTGR named as Clean Burn, which has a high nuclear proliferation resistance, had been proposed by Japan Atomic Energy Agency. In addition to the high nuclear proliferation resistance, in order to enhance the safety, we propose to introduce PuO$$_{2}$$-YSZ TRISO fuel with ZrC coating to the Clean Burn. In this study, we conduct fabrication tests aiming to establish the basic technologies for fabrication of PuO$$_{2}$$-YSZ TRISO fuel with ZrC coating. Additionally, we conduct a quantitative evaluation of the security for the safety, a design of the fuel and the reactor core, and a safety evaluation for the Clean Burn to confirm the feasibility. This study is conducted by The University of Tokyo, Japan Atomic Energy Agency, Fuji Electric Co., Ltd., and Nuclear Fuel Industries, Ltd. It was started in FY2014 and will be completed in FY2017, and the first year of the implementation was on schedule.

Journal Articles

Experiences on research reactors decommissioning in the NSRI of the JAEA

Tachibana, Mitsuo; Kishimoto, Katsumi; Shiraishi, Kunio

International Nuclear Safety Journal (Internet), 3(4), p.16 - 24, 2014/11

Three research reactors were permanently shut down in the Nuclear Science Research Institute (NSRI) of the Japan Atomic Energy Agency (JAEA) as of October 2014. Safe storage or one-piece removal method was applied to decommissioning of these research reactors depending on decommissioning cost and utilization of facilities and so on. Various kinds of data and experiences were obtained through decommissioning of these research reactors. This report shows data and experiences on the research reactors decommissioning in the NSRI of the JAEA.

JAEA Reports

Clearance of concrete generated from modification activities of JRR-3; Investigation of contamination situation of concrete

Satoyama, Tomonori; Kishimoto, Katsumi; Takaizumi, Hirohide; Hoshi, Akiko; Okoshi, Minoru; Tachibana, Mitsuo

JAEA-Technology 2009-060, 42 Pages, 2010/01

JAEA-Technology-2009-060.pdf:4.17MB

In the modification activities of JRR-3, a large volume of extremely low-level radioactive concrete debris were generated from dismantling of concrete structure around reactor body during one-piece removal of reactor body. These concrete debris are stored in the waste storage facility NL of the Nuclear Science Research Institute. The applicability of clearance to concrete debris generated from the modification activities of JRR-3 was examined as waste measures in the Nuclear Science Research Institute. First, generated place, amount of volume and radioactivity of concrete debris in the waste storage facility NL were surveyed from records in the modification of JRR-3 and data sheets of radioactive waste stored in the waste storage facility. Next, the radioactivity of samples taken from concrete debris stored in the waste storage facility NL was measured, and distribution of those radioactivity concentration was investigated to evaluate the contamination situation. In addition, activated contamination situation of concrete structure was evaluated by activated calculation. As a result, radioactivity of concrete debris was enough lower than clearance levels, so it was found that concrete debris in the waste storage facility NL was able to treat as clearance materials.

JAEA Reports

Study on high-performance fuel cladding materials; Joint research report in FY 1999-2000 (Phase 1) (Joint research)

Kiuchi, Kiyoshi; Ioka, Ikuo; Tachibana, Katsumi; Suzuki, Tomio; Fukaya, Kiyoshi*; Inohara, Yasuto*; Kambara, Shozo; Kuroda, Yuji*; Miyamoto, Satoshi*; Ogura, Kazutomo*

JAERI-Research 2002-008, 63 Pages, 2002/03

JAERI-Research-2002-008.pdf:7.85MB

no abstracts in English

Journal Articles

Fatigue behavior on weldment of austenitic stainless steel for ITER vacuum vessel

Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Koizumi, Koichi; Nakahira, Masataka; Takahashi, Hiroyuki*

Fusion Engineering and Design, 58-59, p.869 - 873, 2001/11

 Times Cited Count:1 Percentile:12.3(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Fatigue strength reduction factor of partial penetration weldments for ITER vacuum vessel

Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Nakahira, Masataka

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08

Fatigue test of the weldments was performed to investigate their fatigue behavior and the effect of the incomplete penetrations on the fatigue strength. Fatigue crack propagation test of their weld metals was also carried out using CT specimen. By calculating stress intensity factors of the weldments contained the incomplete penetrations and cracks using FEM analysis, the fatigue crack propagation rates of weldments were evaluated and compared those of their weld metals. Fatigue life of the weldments was evaluated based on fracture mechanics to discuss the effect of incomplete penetrations on the fatigue strength. As the results, the incomplete penetration behaved as a crack and most of total fatigue life for the weldment was crack propagation life. The crack propagation rates of weldment were in accordance with those of the weld metals. The fatigue strength of the weldment was considerably lower than that of smoothed specimen. The incomplete penetrations affected greatly the fatigue strength of the weldments even if the depth of incomplete penetrations was small.

Journal Articles

High temperature tensile properties of metallic materials exposed to a sulfuric acid decomposition gas environment

Kurata, Yuji; Tachibana, Katsumi; Suzuki, Tomio

Nihon Kinzoku Gakkai-Shi, 65(4), p.262 - 265, 2001/04

no abstracts in English

JAEA Reports

Development of experimental apparatus for evaluating corrosion resistance of clasing materials applied for advanced power reactor, 1

Inohara, Yasuto*; Ioka, Ikuo; Fukaya, Kiyoshi; Tachibana, Katsumi; Suzuki, Tomio; Kiuchi, Kiyoshi; Kuroda, Yuji*; Miyamoto, Satoshi*

JAERI-Tech 2001-021, 22 Pages, 2001/03

JAERI-Tech-2001-021.pdf:3.14MB

no abstracts in English

JAEA Reports

Creep strength of Hastelloy XR welded joints

Tachibana, Katsumi; Nishi, Hiroshi; Eto, Motokuni;

JAERI-Tech 99-024, 65 Pages, 1999/03

JAERI-Tech-99-024.pdf:3.01MB

no abstracts in English

JAEA Reports

Creep characteristics of Alloy 800H

Tachibana, Katsumi; Nishi, Hiroshi; Eto, Motokuni;

JAERI-Tech 98-010, 107 Pages, 1998/03

JAERI-Tech-98-010.pdf:3.52MB

no abstracts in English

Journal Articles

The Leakage flow experiments of the seal mechanism for HTGR core suppost blocks

; Takizuka, Takakazu; ; Tachibana, Katsumi;

Nihon Genshiryoku Gakkai-Shi, 30(5), p.433 - 442, 1988/00

no abstracts in English

JAEA Reports

Forced-vibrational test for the support post structure of HTTR

Futakawa, Masatoshi; Kikuchi, Kenji; ; Tachibana, Katsumi

JAERI-M 87-082, 17 Pages, 1987/06

JAERI-M-87-082.pdf:0.73MB

no abstracts in English

Oral presentation

Application of CLEVES to clearance activity of JRR-3 concrete

Tachibana, Mitsuo; Ishigami, Tsutomu; Satoyama, Tomonori; Kishimoto, Katsumi

no journal, , 

no abstracts in English

13 (Records 1-13 displayed on this page)
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