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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
Torii, Tatsuo*; Sanada, Yukihisa; Sato, Yuki
Nihon Genshiryoku Gakkai-Shi ATOMO, 64(1), p.17 - 22, 2022/01
Ten years have passed since the accident at the Fukushima Daiichi Nuclear Power Station. Due to the accident, radioactive materials were widely diffused and deposited not only in the building and site of the Fukushima Daiichi Nuclear Power Station but also in the environment. Demand has increased, and the introduction and development of radiation imaging equipment called gamma cameras and mapping of radiation distribution in the environment have been promoted. Here, we will introduce the radiation distribution measurement technology that has been developed and operated after the accident, and describe the future prospects.
Sasaki, Miyuki
Isotope News, (778), p.2 - 5, 2021/12
no abstracts in English
Sanada, Yukihisa
Fukushima Inobeshon, Kosuto Koso, Hama Dori No Mirai O Hiraku Jitsuyoka Kaihatsu Purojekuto 2018-Nendoban, P. 35, 2019/05
no abstracts in English
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.
Harada, Akio; Sato, Tadashi*; Nakajima, Kunihisa; Komuro, Yuichi; Shiraishi, Hirotsugu*; Hattori, Takamitsu; Ikuta, Yuko; Yachi, Shigeyasu; Kushita, Kohei
JAERI-Review 2005-026, 55 Pages, 2005/09
JAERI-Review-2005-026.pdf:1.95MB
This report provides an example of answers to the problems of the 37th Examination for the Chief Engineer of Nuclear Fuel. This examination was done as a national qualification in March 2005. Brief explanations or references are added to some answers.
Yachi, Shigeyasu; Nakamura, Jinichi; Amaya, Masaki; Nakajima, Kunihisa; Komuro, Yuichi; Nakajima, Katsuaki*; Kobayashi, Yasuhiko; Sato, Tadashi*; Suga, Shinichi*; Noguchi, Hiroshi; et al.
JAERI-Review 2004-020, 61 Pages, 2004/09
JAERI-Review-2004-020.pdf:1.85MB
This report provides an example of answers to the problems of the 36th Examination for the Chief Engineer of Nuclear Fuel. This examination was done as a national qualification in March 2004. Brief explanations or references are added to some answers.
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
Kanamori, Masashi
JNC TN8440 2001-018, 50 Pages, 2001/12
JNC-TN8440-2001-018.pdf:1.31MB
On September 30 at around 10:35 AM, criticality accident occurred at the JCO's conversion building in Tokai-mura. Since criticality accident had not been anticipated, neither devices for termination of criticality accident nor neutron detectors were available. Immediately after the information of the accident, our emergency staff (Japan Nuclear cycle development institute staff) went to JCO site, to measure the intensity of neutrons and gammas. There were four main tasks, first one was to measure the radiation intensity, second one was to terminate the criticality accident, third one is to alert the residents surrounding the JCO site, fourth one is to evacuate the employees in the site. These tasks were successfully performed until October 1. This paper describes about how these operations were performed by the relevant staffs.
Mori, Tomoaki*; Takemura, Morio*
JNC TJ9450 2000-001, 96 Pages, 2000/03
JNC-TJ9450-2000-001.pdf:2.04MB
This report is intended to make it easier to apply the measured data obtained from the Special Materials Experiment, which was conducted at the Oak Ridge National Laboratory (ORNL) during about a month beginning at the end of June, 1992 as the last one of a series of eight experiments planned for the Japanese-American Shielding Program for Experimental Research (JASPER) which was started in 1986. For this reason. the information presented includes specifications and measurement data for all configurations, compositions of all materials, characteristics of the measurement system. and daily-basis records of measurements. The Special Materials Experiment was planned to obtain the data of neutron attenuation characteristics of selected shielding materials for use in advanced fast reactors. The material of particular interest for the experiment was zirconium hydride that is rich in hydrogen. The mockup slabs for the special materials were preceded by the spectrum modifier behind the TSR-II reactor of Tower Shielding Facility. The layer of zirconium hydride was simulated with a combination of zirconium and polyethylene slabs. The thick layer of polyethylene with no zirconium was installed in some configurations.Neutron flux was measured behind the configurations with various types of detectors. The integral neutron flux in wide energy region was measured in eight configurations and neutron spectrum in high energy region was measured also in almost all configurations. Information presented in this report is based mainly on a report issued by ORNL (ORNL/TM-12277. "Measurements for the JASPER Program Special Materials Experiment"). Additional information reported by the assignee is utilized also.
Sawamura, Sadashi*
JNC TJ1400 99-002, 73 Pages, 1999/03
no abstracts in English
Sawamura, Sadashi*
PNC TJ1600 96-003, 77 Pages, 1996/03
no abstracts in English
Mippu Sengen No Kiso; Dai-2-Shu Hoshasen Toriatsukai Shuninsha Shiken No Yoten, 0, p.33 - 99, 1996/00
no abstracts in English
Sawamura, Sadashi*
PNC TJ1600 95-004, 51 Pages, 1995/03
no abstracts in English
Minami, Kentaro
Dekomisshoningu Giho, (6), p.13 - 19, 1992/11
no abstracts in English
