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Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.
Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07
This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.
Asakura, Kazuki; Shimomura, Yusuke; Donomae, Yasushi; Abe, Kazuyuki; Kitamura, Ryoichi; Miyakoshi, Hiroyuki; Takamatsu, Misao; Sakamoto, Naoki; Isozaki, Ryosuke; Onishi, Takashi; et al.
JAEA-Review 2021-020, 42 Pages, 2021/10
JAEA-Review-2021-020.pdf:2.95MB
The disposal of radioactive waste from the research facility need to calculate from the radioactivity concentration that based on variously nuclear fuels and materials. In Japan Atomic Energy Agency Oarai Research and Development Institute, the study on considering disposal is being advanced among the facilities which generate radioactive waste as well as the facilities which process radioactive waste. This report summarizes a study result in FY2020 about the evaluation method to determine the radioactivity concentration in radioactive waste on Oarai Research and Development Institute.
Michino, Masanobu; Suzuki, Toshiaki; Aita, Tsuyoshi; Suto, Masayoshi; Saito, Takakazu; Kawahara, Hirotaka; Isozaki, Kazunori; Ito, Hideaki; Inoue, Setsunari; Aoki, Hiroshi; et al.
JNC TN9430 2004-001, 103 Pages, 2004/03
JNC-TN9430-2004-001.pdf:4.06MB
This report describes the results of the primary and secondary cooling system interlock test and the fuel handling system function test, which were done as a part of JOYO MK-3 function test. The items of the test are: (1) Primary and secondary cooling system interlock test (SKS-106,210) (2) Loss of electric power supply test (SKS-116) (3) In-vessel and ex-vessel automatic fuel transportation test (SKS-501,502) As the interlock of the primary and secondary cooling system was changed, the interlock test by the reactor scram and the loss of electric power supply was carried out. The function of the remote automatic fuel handling system was confirmed before the handling of the fuel for MK-3 core configuration. The results of the test satisfied the required performance, and it was confirmed that operation of the primary and secondary cooling system interlock and operation of the fuel handling system in JOYO MK-3 were normal.
Ishii, Takayuki; Isozaki, Kazunori; Ashida, Takashi; Minakawa, Satoru; Terakado, Tsuguo; Nogami, Hiroshi*; Kakurai, Katsuhiko*; Ueda, Soji*; Kawahara, Hirotaka; Ichige, Satoshi; et al.
JNC TN9410 2002-013, 86 Pages, 2002/11
JNC-TN9410-2002-013.pdf:68.29MB
The MK-III project has been proceeding to improve the irradiation capability of the experimental fast reactor JOY0. The MK-III project has three major purposes such as increase high neutron flux, improvement of plant availability factor and upgrading in irradiation techniques. Thermal output by core transformation for high neutron flux was increased from 100MWt to 140MWt. The main components in the cooling system such as IHX(Intermediate Heat Exchanger) and DHX(Dump Heat Exchanger) were replaced in MK-III modification in order to increase heat removal capability. Heat transfer capacity of IHX was increased from 50MWt/Unit to 70MWt/Unit and that of DHX was increased from 25MWt/Unit to 35MWt/Unit. These components replacement has been safety completed from october 30, 2000 through September 21, 2001. This report summarizes the way, results and safety measures about dismantling of no sodium adhered components and such as DHX blower and sodium cleaning of sodium components such as the DHX, the pipes connected with DHX and secondary side of IHX. Dismantling and sodium cleaning of secondary cooling system components were performed safely and efficiently as almost planned. The total amount of removed sodium was about 13.5kg.
Isozaki, Kazunori; Ogawa, Toru; Kubo, Atsuhiko; Sugaya, Kazushi*; Aoki, Hiroshi; Ozawa, Kenji
PNC TN9410 98-055, 92 Pages, 1998/05
Scrutiny based on the convenient evaluation to verify whether we have the place where thermal striping in the pipe confluence part was thought to be a primary factor for the heavy accident or not has been done in JOYO. As the result, the big temperature difference (
Tin) of the simple inner pipe confluence part existed at the inner pipe confluence part of the plugging system in the secondary main and auxiliary cooling system. Therefore, detailed evaluation of thermal striping was needed. With the thermocouples of high response installed, the temperature fluctuation in outer surface of the pipe was measured on the secondary auxiliary plugging system for the reason why the temperature difference (Tin) was the biggest. And, the temperature fluctuation in inner surface of the pipe and stress occurring in the pipe plate thickness direction was evaluated by means of the temperature fluctuation measurement result and non-linear structure analysis system "FINAS". The above-mentioned evaluation results were as follows. (1)The maximum temperature fluctuation occurring in the pipe was always located from the center of inner pipe confluence to 10mm position of the down-stream side. (2)The maximum temperature fluctuation range was about 33
C in outer surface of the pipe. And, controlling frequency of the temperature fluctuation was 0.04Hz and 0.09Hz. (3)Time delay was almost never contained in the temperature fluctuation elements between inner and outer surface of the pipe by dint of analysis results of the heat conduction by "FINAS". And, the big temperature distribution did not occur in the pipe plate thickness direction was confirmed that the big temperature distribution did not occur in the pipe plate thickness direction. (4)The temperature fluctuation in the pipe inner surface and the stress occurring in the pipe plate thickness direction was evaluated by use of result of the temperature fluctuation measurement and the heat conduction ...
Fukuda, Seiji; Kato, Jinzo; Onishi, Takeshi; Watanabe, Kozo; Okubo, Katsuichi; Ouchi, Masafusa; Isozaki, Hiroshi; Seki, Mamoru; Mito, Norio; Tsuruo, Akira; et al.
JAERI 1028, 55 Pages, 1962/10
no abstracts in English
Nakai, Ryodai; Kurisaka, Kenichi; Sato, Ikken; Tobita, Yoshiharu; Kamiyama, Kenji; Yamano, Hidemasa; Miyahara, Shinya; Ohno, Shuji; Seino, Hiroshi; Ishikawa, Hiroyasu; et al.
no journal, ,
To develop a core damage evaluation technology (level-2 PSA) in sodium-cooled fast reactors, a new analysis method is developed for core-material relocation phase and internal containment vessel event. This study also develop technical basis necessary for the level-2 PSA.
Seino, Hiroshi; Ishikawa, Hiroyasu; Ohno, Shuji; Kawaguchi, Munemichi; Isozaki, Mikio; Miyahara, Shinya
no journal, ,
As a part of development of the core damage evaluation technology (level 2 PSA), validation studies were carried out to improve the analytical accuracy for the sodium-concrete reaction model in CONTAIN/LMR.
