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Tanimura, Yoshihiko; Yoshitomi, Hiroshi
Nihon Genshiryoku Gakkai-Shi ATOMO
, 66(1), p.42 - 45, 2024/01
no abstracts in English
Yoshitomi, Hiroshi
Isotope News, (786), p.26 - 29, 2023/04
no abstracts in English
Tsuda, Shuichi; Tanigaki, Minoru*; Yoshida, Tadayoshi; Saito, Kimiaki
Hoshasen, 44(3), p.109 - 118, 2018/11
JAEA has started to perform dose rate monitoring using a car-borne survey system KURAMA to rapidly produce the dose rate mappings of the deposited radionuclides in the environment after the Fukushima Dai-ichi Nuclear Power Plant accident. KURAMA is a car-borne survey system developed by Kyoto University to perform dose rate monitoring in a wide area in detail with rapidity. By improving KURAMA with continuous dose rate monitoring, the 2nd generation of KURAMA (KURAMA-II) succeeded in downsizing, durability and automated transmission of data so that enable detailed dose rate mapping in wide area in shorter period of time. This paper reports the radiation characteristics and the simulation analysis of KURAMA-II on the special issue of Hoshasen, the journal of Ionization Radiation Division in the Japan society of applied physics.
Radiation Protection Department
JAEA-Review 2015-003, 187 Pages, 2015/03
JAEA-Review-2015-003.pdf:18.34MB
This annual report summarizes the various activities on radiation control at the nuclear fuel cycle facilities in Nuclear Fuel Cycle Engineering Laboratories, which were undertaken by the Radiation Protection Department in fiscal 2009. In the Laboratories, the Tokai Reprocessing Plant (TRP), MOX fuel fabrication facilities, the Chemical Processing Facility (CPF), and various other radioisotopes and uranium research laboratories have been operated. The Radiation Protection Department is responsible for the radiation control in and around the facilities, including personnel monitoring, workplace monitoring, consultation on radiological work planning and evaluation, monitoring of gaseous and liquid waste effluents, environmental monitoring, radiological standards, maintenance of radiation monitoring instruments, quality management, and the related research. In fiscal 2009, the results of radiological monitoring showed the situation to be normal, and no radiological incident or accident occurred. The maximum annual effective dose to radiation workers was 9.7 mSv and the mean annual effective dose was 0.2 mSv. Individual doses were kept within the annual dose limit specified in the safety regulations. The estimated effective dose caused by gaseous and liquid effluents from the TRP to imaginary members of the public around the Laboratories was 1.8
10
mSv. The environmental monitoring and effluent control were performed appropriately in compliance with safety regulation and standards. As for the quality management activities, the inspection by the government, the internal audit, and the maintenance to revise the documents have been continued in accordance with the quality management system which had been introduced to safety regulation since fiscal 2004.
Yagisawa, Hiroshi; Arai, Takashi; Goto, Yoshitaka*
Heisei-16-Nendo Osaka Daigaku Sogo Gijutsu Kenkyukai Hokokushu (CD-ROM), 4 Pages, 2005/03
no abstracts in English
Murakami, Hiroyuki; Minami, Kentaro*
Radioisotopes, 53(3), p.197 - 205, 2004/03
no abstracts in English
Shimizu, Shigeru; Fujii, Katsutoshi; Kajimoto, Yoichi; Kawasaki, Tomokatsu; Yamamoto, Hideaki
Dai-16-Kai Tandemu Kasokuki Oyobi Sono Shuhen Gijutsu No Kenkyukai Hokokushu, p.32 - 35, 2004/02
no abstracts in English
Murakami, Hiroyuki
Hoken Butsuri, 36(4), p.359 - 361, 2001/01
no abstracts in English
Ikezoe, Hiroshi
Genshiryoku Kogyo, 41(3), p.31 - 34, 1995/00
no abstracts in English
Nagaoka, Toshi; Sakamoto, Ryuichi; Saito, Kimiaki; Tsutsumi, Masahiro; Moriuchi, Shigeru
JAERI-M 93-125, 41 Pages, 1993/06
no abstracts in English
Nagaoka, Toshi; Sakamoto, Ryuichi; Saito, Kimiaki; Tsutsumi, Masahiro; Moriuchi, Shigeru
JAERI-M 89-155, 32 Pages, 1989/10
no abstracts in English
N high energy 
-ray irradiation field for calibrating radiation measuring instruments; Minami, Kentaro
Hoken Butsuri, 23, p.27 - 33, 1988/00
no abstracts in English
Shimoyama, Kazuhito; Kuroha, Mitsuo; *
PNC TN9410 87-014, 103 Pages, 1987/01
Acoustic type water leak detectors have promising potentiality in short detection time for minimising the extent of tube failure propagation caused by water leakage from a heat transfer tube of an LMFBR steam generator. Two different methods as follows were studied in this program : (1)The method to compare effective values between water leak sound and back ground noise using a single channel. (2)The method to detect and locate the leak using cross correlation signal processing of multi-channel. In the former one, it was estimated from acoustic signals obtained in the 50 MW Steam Generator Test Facility that the back ground noise levels of the Prototype and the Demonstration reactor were 0.0093G and 0.012G (G=gravity), respectively. The water leak rates equivalent to those back ground levels were evaluated as approximately 0.7 and 7 g/sec. In the latter one, first a detection and location software was developed in a off-line analysis, and secondly an on-line signal processing hardware was manufactured as a trial. In the off-line analysis, the influence of the internals on detection performance was examined by horizontal and vertical measurement. As the result, it revealed that back ground noise interfered the leak detection and location and that the potential depended on the leak positions even without noise. In the on-line analysis, leaks in a lower plenum were detectable with the same accuracy as the off-line analysis.
