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Okumura, Keisuke
Fission Product Behavior under Severe Accident, p.116 - 121, 2021/05
no abstracts in English
Ishigaki, Masahiro; Abe, Satoshi; Shibamoto, Yasuteru; Yonomoto, Taisuke
Nuclear Engineering and Design, 367, p.110790_1 - 110790_15, 2020/10
Times Cited Count：14 Percentile：84.32(Nuclear Science & Technology)no abstracts in English
Hamdani, A.; Abe, Satoshi; Ishigaki, Masahiro; Shibamoto, Yasuteru; Yonomoto, Taisuke
Energies (Internet), 13(14), p.3652_1 - 3652_22, 2020/07
Times Cited Count：6 Percentile：18.77(Energy & Fuels)Ishigaki, Masahiro; Abe, Satoshi; Shibamoto, Yasuteru; Yonomoto, Taisuke
Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.5927 - 5940, 2019/08
no abstracts in English
Okumura, Keisuke; Riyana, E. S.; Sato, Wakaei*; Maeda, Hirobumi*; Katakura, Junichi*; Kamada, So*; Joyce, M. J.*; Lennox, B.*
Progress in Nuclear Science and Technology (Internet), 6, p.108 - 112, 2019/01
In order to establish the prediction method of the dose rate distribution in the primary containment vessel (PCV) of the Fukushima Daiichi Nuclear Power Station, a series of calculations were carried out in the following way; (1) burnup calculation to obtain fuel composition at the time of accident, (2) activation calculation for the structural materials including impurities, (3) estimation of Cs contamination in PCV based on the result of severe accident analysis by IRID, (4) decay calculation of radioactive nuclides, (5) photon transport calculation to obtain dose rate distribution. After that, Cs concentration around the dry-well of 1F was modified to be consistent with locally measured dose rates in the PCV-investigation by IRID.
Ichikawa, Shoichi; Chiba, Yusuke; Ono, Fumiyasu; Hatori, Masakazu; Kobayashi, Takanori; Uekura, Ryoichi; Hashiri, Nobuo*; Inuzuka, Taisuke*; Kitano, Hiroshi*; Abe, Hisashi*
JAEA-Research 2016-021, 32 Pages, 2017/02
JAEA-Research-2016-021.pdf:5.0MB
In order to reduce the influence on a plant schedule of the MONJU by the maintenance of dew point hygrometers, The JAEA examined a capacitance type dew point hygrometer as an alternative dew point hygrometer for a lithium-chloride type dew point hygrometer which had been used at the CV-LRT in the MONJU. As a result of comparing a capacitance type dew point hygrometer with a lithium-chloride type dew point hygrometer at the CV-LRT (Atmosphere: nitrogen, Testing time: 24 hours), there weren't significant difference between a capacitance type dew point hygrometer and a lithium-chloride type dew point hygrometer. As a result of comparing a capacitance dew point hygrometer with a high-mirror-surface type dew point hygrometer for long term verification (Atmosphere: air, Testing time: 24 months), the JAEA confirmed that a capacitance type dew point hygrometer satisfied the instrument specification (
2.04
C) required by the JEAC4203-2008.
Miyahara, Shinya; Seino, Hiroshi; Ohno, Shuji; Konishi, Kensuke
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 5 Pages, 2015/05
A CONTAIN-LMR code has been developed in JAEA for application to PRA of LMFRs since the original CONTAIN code had been introduced from SNL of U.S. in 1982. The code is a best-estimate, integrated analysis tool for predicting the physical, chemical and radiological conditions inside a containment building of LMFRs following a severe accident with reactor vessel melt-through. The code is also able to predict the source term to the environment in the accident. This code can treat many important phenomena consistently such as sodium fire, radioactive aerosol behavior, hydrogen burn, sodium-concrete reaction and core debris-concrete interaction occurred in the accident with inter-cell heat and mass flow under the multiple cell geometry. This paper describes the chronology of the code development in JAEA briefly as an introduction, and after that, the outline of computational models in the code, the examples of the code validation, and the future plan of the code application are described.
Saito, Kazuo*; Kusunoki, Tsuyoshi; Ishida, Toshihisa
JAERI-Tech 2001-038, 100 Pages, 2001/06
JAERI-Tech-2001-038.pdf:6.02MB
no abstracts in English
Nakazawa, Takashi; Kikuchi, Hisaki; Yasu, Katsuji; Yoshino, Toshiaki; Ashikagaya, Yoshinobu; Sato, Koichi; Minowa, Yuji; Nomura, Toshibumi
JAERI-Tech 2001-010, 125 Pages, 2001/03
no abstracts in English
Nakazawa, Takashi; Yoshino, Toshiaki; Yasu, Katsuji; Ashikagaya, Yoshinobu; Kikuchi, Hisaki
JAERI-Tech 2001-001, 101 Pages, 2001/02
JAERI-Tech-2001-001.pdf:5.15MB
no abstracts in English
Kaminaga, Masanori; Terada, Atsuhiko*; Haga, Katsuhiro; Kinoshita, Hidetaka; Ishikura, Shuichi*; Hino, Ryutaro
JAERI-Tech 2000-076, 70 Pages, 2001/01
JAERI-Tech-2000-076.pdf:4.01MB
no abstracts in English
Kusunoki, Tsuyoshi; Ito, Toshio*; Nariai, Hideki*
Nihon Kikai Gakkai 2000-Nendo Nenji Taikai Koen Rombunshu, p.645 - 646, 2000/08
no abstracts in English
Sobajima, Makoto
IAEA-TECDOC-1002, p.27 - 36, 1998/03
no abstracts in English
Fune No Kagaku, 51(1), p.68 - 74, 1998/01
no abstracts in English
Kusunoki, Tsuyoshi; Yoritsune, Tsutomu; Ishida, Toshihisa
Nihon Genshiryoku Gakkai-Shi, 40(2), p.135 - 143, 1998/00
Times Cited Count：1 Percentile：15.03(Nuclear Science & Technology)no abstracts in English
Kusunoki, Tsuyoshi; *; Yoritsune, Tsutomu; ; Ishida, Toshihisa
JAERI-Tech 97-046, 56 Pages, 1997/09
no abstracts in English
Sobajima, Makoto
Nihon Genshiryoku Gakkai-Shi, 39(7), p.560 - 562, 1997/00
no abstracts in English
