Annual report on the present state and activities of the Radiation Protection Department, Nuclear Fuel Cycle Engineering Laboratories in fiscal 2009

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 1.810 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.

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PNC TN8440 94-025, 112 Pages, 1994/03

PNC-TN8440-94-025.pdf:2.99MB

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PNC TN8440 94-007, 106 Pages, 1993/12

PNC-TN8440-94-007.pdf:2.63MB

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PNC TN8440 92-039, 104 Pages, 1992/06

PNC-TN8440-92-039.pdf:2.58MB

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PNC TN8440 92-013, 104 Pages, 1991/12

PNC-TN8440-92-013.pdf:2.58MB

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Radiation management for the remodeling work of STACY

Nakajima, Junya; Yamada, Katsunori; Hasegawa, Rie; Umeda, Masayuki; Seki, Masakazu; Muto, Yasushi; Sawahata, Katsunori

no journal, , 

STACY (Static Experiment Critical Facility) has been under remodeling work. During the demolition work of the previous model of STACY, we conducted radiation management for both internal exposure and external exposure taking the characteristics of the previous model into consideration. As a result, any contamination and internal exposure of the all workers was detected, and external exposure of the all workers were less than the detection limit.

Management of worker dose exposure associated with decontamination work, 3; Experience in worker's dose exposure control

Abe, Tomohisa; Sanada, Yukihisa; Tokiyoshi, Masanori*; Nishiyama, Kyohei*; Sato, Rina*; Yoshimura, Kazuya; Funaki, Hironori; Ishida, Mutsushi*; Nagamine, Haruo*; Fujisaka, Motoyuki*

no journal, , 

We attempted to analyze in detail the actual external exposure doses of workers involved in decontamination work, which had been difficult to analyze in detail until now, by recording location information and exposure doses using GPS. As a result, it was found that more than 50% of the planned exposure dose calculated from the air dose rate and the number of actual working hours were more than twice the median the measured exposure doses. Furthermore, analysis by work type showed that the exposure doses of demolition workers tended to be higher. This information on the external exposure dose of workers linked to location information is useful for detailed analysis of external exposure factors and will contribute to the optimization of future radiation protection programs for workers.