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Takeuchi, Ryuji; Nishio, Kazuhisa*; Kokubu, Yoko
JAEA-Data/Code 2023-013, 74 Pages, 2024/01
The Tono Geoscience Center of Japan Atomic Energy Agency (JAEA) has been conducting the environmental monitoring investigation to confirm the environmental impacts associated with the backfilling of shafts and tunnels at the Mizunami Underground Research Laboratory (MIU). This report summarizes the results of the environmental impact investigations conducted as part of the environmental monitoring investigation around the MIU Site in FY2022, which include groundwater level measurement in wells, river flow rate measurement, water analysis of Hazama river, noise and vibration surveys, and soil survey.
Takeuchi, Ryuji; Nishio, Kazuhisa*; Hanamuro, Takahiro; Kokubu, Yoko
JAEA-Data/Code 2022-010, 110 Pages, 2023/03
The Tono Geoscience Center of Japan Atomic Energy Agency (JAEA) has been conducting the environmental monitoring investigation to confirm the environmental impacts associated with the backfilling of shafts and tunnels at the Mizunami Underground Research Laboratory (MIU). This report summarizes the results of environmental impact investigations conducted as part of the environmental monitoring investigation around the MIU Site from FY2020 to FY2021, which include groundwater level measurement in wells, river flow rate measurement, water analysis of Hazama river, noise and vibration surveys, and soil survey.
Kawasaki, Kohei; Shinada, Kenta; Okamoto, Naritoshi; Kageyama, Tomio; Eda, Takashi; Okazaki, Hiro; Suzuki, Hiromichi; Yamamoto, Kazuya; Otabe, Jun
JAEA-Technology 2020-025, 80 Pages, 2021/03
Plutonium Fuel Production Facility was built in 1988 for the purpose of mainly producing MOX fuel of the prototype fast breeder reactor MONJU, and large glove boxes were installed for handling unsealed nuclear fuel material remotely. The panels of these glove boxes are made of acrylic, except for those installed after December 2013. For fires inside the glove box, automatic fire extinguishing systems using halides have been introduced since the beginning of construction, but for fires outside the glove box, there have been issues with direct measures for acrylic. Therefore, we have developed a fireproof sheet that mitigates the effect of fire outside the glove box on the panels as much as possible. As a result, fire-retardant sheets have been selected and attached to the glove box panels. We conducted a flammability test of the acrylic plate attached with these fireproof sheets and a usage environment influence test of fireproof sheets, and obtained good results. In addition, we set up a working group in the Plutonium Fuel Development Center in view of reducing external exposure during the work of attaching fireproof sheets, in which we discussed and examined the work procedure, and summarized it in the basic procedure manual.
Nakamura, Yasuo; Nakatani, Takayoshi
JAEA-Technology 2014-048, 18 Pages, 2015/03
Sodium nitrate is included bituminized waste generating from the reprocessing plant of spent fuel which is disposed of in sub-surface disposal facility. Because the sodium nitrate is soluble material in surface water, it is a concern impact on surface water. Such as non-radioactive materials are not strictly regulated by "the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors", but should be considered by related laws and regulations according to former basic policy. Because it is regulated as nitrate nitrogen by "The Basic Environment Law", the valuation of the environmental impact on general sub-surface disposal system was carried out. As the results, the concentration of nitrate nitrogen in river water whose annual quantity of water is rather than 110m/y is below the regulated value at the small scale surface waters as evaluation point.
Radiation Protection Department
JAEA-Review 2015-003, 187 Pages, 2015/03
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.
Konishi, Satoshi; Okano, Kunihiko*; Tokimatsu, Koji*; Ito, Keishiro*; Ogawa, Yuichi*
Fusion Engineering and Design, 69(1-4), p.523 - 529, 2003/09
Times Cited Count:4 Percentile:31.64(Nuclear Science & Technology)no abstracts in English
Kobayashi, Takuya; Togawa, Orihiko
Proceedings from the International Conference on Radioactivity in the Environment (CD-ROM), 4 Pages, 2002/09
A marine environmental assessment system STEAMER is developing for predicting the short-term (30days) dispersion and assessing the collective dose to the Japanese population due to radionuclides released to the ocean. The computer code system for short-term predictions of radionuclide dispersion is a combination of the Princeton Ocean Model (POM) for predicting ocean currents and a particle random walk model SEA-GEARN for oceanic dispersion of dissolved radionuclides. The system has been applied to a hypothetical accident of a nuclear submarine if it sinks in an offshore region around Japan, by using measured currents, temperature, salinity and meteorological regional objective analysis data (RANAL). Another computer code system DSOCEAN is also applied to the same hypothetical accident in order to compare the results of radionuclide dispersion in the ocean and the collective dose to the Japanese population. An equidistant-grid compartment model combined with a model of the geostrophic current analysis is used in DSOCEAN.
Kobayashi, Hideo
Genshiryoku Nenkan 2001/2002-Nen Ban, p.103 - 105, 2001/11
no abstracts in English
Takebe, Shinichi; Abe, Masayoshi
JAERI-Data/Code 2001-005, 344 Pages, 2001/03
no abstracts in English
Nishiza, Masahiro
Genshiryoku Nenkan 2000/2001-Nen Ban, p.104 - 106, 2000/10
no abstracts in English
; Shinohara, Kunihiko; ; ; ; Isozaki, Tokuju; ; *
JNC TN8440 2000-003, 93 Pages, 2000/08
The investigation on the radioactivity concentration for gross beta, H and Cs in seawater collected around the discharge point had been performed in order to grasp the change of the activity level of the coastal seawater offshore the JNC Tokai Works from the low level liquid effluent of the reprocessing plant. After the investigation on the radioactivity in seawater during the hot examination, the detailed investigation on the environmental effects from the liquid effluent of JNC reprocessing plant has been performed since July 1978 on the basis of the request from Ibaraki prefecture as the full-scale operation of the reprocessing plant. Consequently, no increase of the radioactive concentration due to the discharged effluent has been observed. And also, as the result of the consideration to the investigation on the environmental effect from the liquid effluent throughout 22 years since 1978, no change of the radioactive concentration level in seawater was recognized.
Ono, Takahiro*; Higuchi, Takanao*; Kazama, T.*; Hashimoto, T.*; Seito, Y.*; Hattori, Tomomi*; Kanamori, Miwa*
JNC TJ1420 2000-005, 257 Pages, 2000/03
None
Fujine, Sachio; Murata, Mikio; Abe, Hitoshi; Takada, Junichi; Tsukamoto, Michio; Miyata, Teijiro*; Ida, Masaaki*; Watanabe, Makio; Uchiyama, Gunzo; Asakura, Toshihide; et al.
JAERI-Research 99-056, p.278 - 0, 1999/09
no abstracts in English
Kishimoto, Hiroshi
Genshiryoku eye, 44(9), p.8 - 9, 1998/09
no abstracts in English