高温工学試験研究炉特集に寄せて (3)

第一原子力産業グループ会長　

HTTRの概要 (4)

梅津博幸 / 勝木岳嗣 / 岡本太志

HTTRの炉心設計，安全評価 (9)

渡部　隆 / 大橋一孝 / 木曽芳弘 / 中田哲夫

富士電機のHTTR機器の設計製作 (19)

梅津博幸/ 神谷栄世 / 菅野政男 / 高橋正昭 / 田沢勇次郎

前園伸也 / 児玉健光 / 辻　延昌 / 三木俊也

川崎重工のHTTR機器の設計・製作 (36)

野村陽一 / 勝木岳嗣 / 佐藤康士 / 野地喜吉 / 森雄一郎 / 内川　直

河江秀俊 / 斎藤利二 / 妹尾直介 / 井上教之 / 古野修作 / 藤塚　勝

HTTR初装荷燃料の製造 (47)

加藤　茂 / 吉牟田秀治 / 羽角　孝 / 佐藤建治 / 沢　和弘

鈴木修一 / 茂木春義 / 塩沢周策 / 田中利幸

■ グループ情報

FAPIGの機構 (52)

表紙デザイン：中村加奈女

CONTENTS

−Special Issue for "HTTR"−

Preface (3)

Kunihiko Sawa

Overview of High Temperature Engineering Test Reactor (HTTR) (4)

H. Umetsu / T. Katsuki / F. Okamoto

Core Design and Safety Evaluation of HTTR (9)

T. Watanabe / K. Ohashi / Y. Kiso / T. Nakata

Design and Construction of Equipments for High Temperature

Engineering Test Reactor (HTTR) (19)

H. Umetsu / E. Kamiya / M. Kanno / M. Takahashi / Y. Tazawa

S. Maezono / T. Kodama / N. Tsuji / T. Miki

Design and Fabrication of HTTR Components by Kawasaki Heavy Industries, LTD (36)

Y. Nomura / T. Katsuki / K. Satou / K. Noji / Y. Mori

T. Uchikawa / H. Kawae / T. Saitou / N. Seo / N. Inoue

S. Furuno / M. Fujitsuka

Fabrication of HTTR First Loading Fuel (47)

S. Kato / S. Yoshimuta / T. Hasumi / K. Sato / K. Sawa

S. Suzuki / H. Mogi / S. Shiozawa / T. Tanaka

Cover Design：Kaname Nakamura

Hiroyuki Umetsu, Taketsugu Katsuki, Futoshi Okamoto

Overview of High Temperature Engineering Test Reactor (HTTR)

FAPIG No. 154 pp. 4〜 8 (2000)

　The HTTR with the thermal output of 30MW and the outlet gas temperature of 950 C developed by Japan Atomic Energy Research Institute (JAERI) is a first High-Temperature Gas Cooled Reactor in Japan. The aim of the HTTR is to carry out the necessary R&D for establishing and upgrading HTGR technology and to conduct various innovative basic researches on high temperature technologies.

　The application for the construction permit of the HTTR was submitted to Science and Technology Agency (STA) in February 1989 and was permitted in November 1990.The construction was started in March 1991 and completed in September 1997 as scheduled. Fuel loading and criticality test was started in the middle of 1998. First criticality was achieved in November 10,1998 and full core loading was completed in December 1998. After the non-nuclear heat up test, JAERI has started the rise to power test in September 1999.

KEYWORDS：HTGR, HTTR, development, construction, commissioning test

Takashi Watanabe, Kazutaka Ohashi, Yoshihiro Kiso, Tetsuo Nakata

Core Design and Safety Evaluation of HTTR

FAPIG No. 154 pp. 9〜18 (2000)

　Fuji Electric Co. Ltd. and Kawasaki Heavy Industries, Ltd. cooperated with Japan Atomic Energy Research Institute (JAERI) for the core design and safety evaluation of HTTR.

　The HTTR is characterized by the high outlet temperature of 950℃. Main features of core design to attain this such as the reactivity control, the fuel loading and the core flow distribution plan are reported.

　Selecting core depressurization accident as a typical example of HTTR accident, main features of HTTR safety evaluation such as simulation programs, used data and analyzed results are reported following this accident sequences.

KEYWORDS：HTTR, core design, reactivity control, fuel loading, flow control, safety evaluation, depressurization accident, pressure of containment, graphite oxidation, fp release, exposure

Hiroyuki Umetsu, Eisei Kamiya, Masao Kanno, Masaaki Takahashi, Yujiro Tazawa, Shinya Maezono, Takemitsu Kodama, Nobumasa Tsuji, Toshiya Miki

Design and Construction of Equipments for High Temperature Engineering Test Reactor (HTTR)

FAPIG No. 154 pp. 19〜 35 (2000)

　Fuji Electric Co., Ltd. contributed to the construction of the HTTR as a supplier of some main equipments, the reactor internals, the fuel handling and storage system and the fuel handling machine including instrumentation and control system, the radiation monitoring system etc. Fuji Electric was expected to show the technological potential accumulated through the development and conceptual design of those equipments.

Fuji Electric had been going ahead with the design, manufacturing and quality assurance activities of those equipments and completed successfully installation and testing in September 1997.

This paper describes the outline of those equipments and Fujiﾕs activities around the construction.

KEYWORDS：HTGR, HTTR, reactor internals, fuel handling and storage system, fuel handling machine, radiation monitoring system, construction, manufacture, quality assurance

Youichi Nomura, Taketsugu Katsuki, Kouji Satou, Kiyoshi Noji, Yuichirou Mori, Tadashi Uchikawa, Hidetoshi Kawae, Toshiji Saitou, Naosuke Seo, Noriyuki Inoue, Shuusaku Furuno, Masaru Fujitsuka

Design and Fabrication of HTTR Components by Kawasaki Heavy Industries, LTD

FAPIG No. 154 pp. 36 〜46 (2000)

　Developed by Japan Atomic Energy Research Institute, HTTR reached the critical point for the first time,on 10th of November 1998, and is now under examination for raising power to 100% operation.

　Kawasaki Heavy Industries, LTD has been engaged in construction of HTTR, in charge of designing and manufacturing of various facilities.

　We are taking this opportunity to review our designing and manufacturing of facilities, in the FAPIG magazine.

KEYWORDS：high temperature engineering test reactor, replaceable reflector block, control rod guide block, auxiliary cooling system, new fuel storage rack, new fuel handling and inspection system, spent fuel storage pool cooling system, fuel failure detection system, precipitator

Shigeru Kato, Shigeharu Yoshimuta, Takashi Hasumi, Kenji Sato, Kazuhiro Sawa, Shuichi Suzuki, Haruyoshi Mogi,

Shusaku Shiozawa, Toshiyuki Tanaka

Fabrication of HTTR First Loading Fuel

FAPIG No. 154 pp. 47〜51 (2000)

　Fabrication of the first loading fuel for HTTR (High Temperature engineering Test Reactor) constructed by JAERI (Japan Atomic Energy Research Institute) started at HTR fuel facility of NFI (Nuclear Fuel Industries, Ltd.) June 1995. 4,770 fuel rods were fabricated through the fuel kernel, coated fuel particle and fuel compaction process, then 150 fuel elements were assembled in the reactor building December 1997.

　Fabrication technology for the fuel was established through a lot of R＆D activities and fabrication experience of irradiation examination samples spread over about 30 years. Most of all, very high quality and production efficiency of fuel were achieved by the development of the fuel kernel process using the vibration dropping technology, the continuous 4-layer coating process and the automatic compaction process. The quality of the first loading fuel fully satisfied the design specifications for the fuel. In particular, average free uranium fraction and SiC defective fraction of fuel compacts were ２×10−6 and ８×10−5 respectively.

KEYWORDS：HTTR, first loading fuel, coated fuel particle

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