Practical action levels for chelation therapy in plutonium inhalation using nose swab

Kurihara, Osamu; Takada, Chie; Takasaki, Koji; Ito, Kimio; Momose, Takumaro; Miyabe, Kenjiro

Radiation Protection Dosimetry, 127(1-4), p.411 - 414, 2007/11

https://doi.org/10.1093/rpd/ncm295

Practical action levels for beginning chelation therapy to remove plutonium in the body are now under discussion in Japan since there has been no experience in administrating agents to a subject in accidental intake in Japan although a first commercial reprocessing plant is about to start operation. Recently, International Commission on Radiological Protection (ICRP) proposed some medical intervention levels for chelation therapy on ICRP Publication 96. These levels are determined based on internal dose however common monitoring methods such as lung counting or excreta analysis are not necessarily suitable in terms of both sensitivity and promptness. As an alternative, the authors paid attention to nose swabs and introduced the practical action levels.

Radiation protection feature and research at nuclear fuel cycle engineering laboratories, JAEA

Furuta, Sadaaki; Miyabe, Kenjiro

Proceedings of 2nd Asian and Oceanic Congress Radiological Protection (AOCRP-2) (CD-ROM), p.928 - 932, 2006/10

In 1972, production of nuclear fuels for experimental fast breeder reactor "JOYO" started at MOX fuel fabrication facilities in the Nuclear Fuel Cycle Engineering Laboratories of JAEA. And in 1977 Tokai reprocessing plant "TRP" was launched as the first nuclear reprocessing plant in Japan with a capacity of 0.7tU/day spent fuel, and successfully reprocessed 1,116tU fuel mainly spent by light water reactor up to March 2006. A lot of other nuclear facilities associated with them are located at the same Laboratories' site. A feature of radiation protection and its recent relevant researches at the Laboratories are described in this paper.

The Support Activities of JNC against the JCO Criticality Accident

Kanamori, Masashi; Kawata, Tomio; Hitoshi, Watanabe,; Tobita, Yoshiharu; Sugiyama, Toshihide; Miyabe, Kenjiro; Kobayashi, Hirohide

JNC TN8450 2003-009, 506 Pages, 2004/03

JNC-TN8450-2003-009.pdf:14.21MB

This paper describes all the activities that were executed by JNC related to JCO criticality accident on September 30,1999. During the JCO accident, the activities of radiation monitoring, environmental monitoring, criticality termination operation, computer simulation of criticality accident, whole body exposure measurements by WBC about 24-Na, back up of local government like consultation of residents near by were performed by JNC. After the accident Japanese government and Nuclear Safety Commission establishes the investigation committee of JCO accident. JNC has also back up this activity. For example, investigation of the causes, accident scenario, estimation of the doses of the workers and personnel for deserter, counter measure operation. This paper summarizes all the important activity executed by JNC in the meantime.

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; Miyabe, Kenjiro; ; Akiyama, Kiyomitsu;

Hoken Butsuri, 37(3), 222- Pages, 2002/09

https://doi.org/10.5453/jhps.37.222

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Measurement of gamma spectrum of radioactive waste and working environment by portable germanium detecter.

Sanada, Yukihisa; Akiyama, Kiyomitsu; *; ; Miyabe, Kenjiro

JNC TN8410 2002-003, 75 Pages, 2002/07

JNC-TN8410-2002-003.pdf:39.78MB

Practical application of portable Ge detector was examined in radiation control at the reprocessing plant. Main purposes of the examination are, (1)estimation of radionuclides inventory by in-situ object counting system (ISOCS), and (2)acquisition of the gamma ray energy information which is necessary for dose estimation. At first waste box, analytical Jug, filter and lead container were measured. Then gamma spectrum was measured around glove box in Pu conversion development facility (PCDF). As a result, some aspects concerned about detection limit, distribution of point source and self-absorption by low energy gamma ray were clarified. Information on the gamma ray energy were obtained. Radiation control will become advanced by measurering a gamma ray spectrum by portable germanium detector.

Decontamination factor of the commerciaI detergents for the skin (Part 3)

Miyabe, Kenjiro; Takasaki, Koji; Yasunaga, Hideo*; Izumi, Yuichi*

JNC TN8420 2000-007, 100 Pages, 2000/08

JNC-TN8420-2000-007.pdf:7.66MB

The commercial detergents, which are cleansing cream, shampoo, neutral detergent, etc., were examined in order to select the body cleaners that are substitutes for the titanium dioxide paste. JNC entrusted Japan Environment Research Corporation Limited with these examinations since 1997. In 1997 and 1998, the commercial detergents were examined for Ce-144, Cs-137 and Ru-106. In 1999, 22 detergents were examined for Co-60 from the result of the past examinations. In this examination, the radioactive solution of Co-60 was dropped on the pig-skin samples. These samples were washed with each detergent after 5 minutes and 40 minutes. The decontamination factors of detergents were estimated by the radioactive ratio of the samples before and after washing. As a result of this examination, the decontamination factors for Co-60 was the same as the decontamination factors for Ce-144 and Cs-137, and 11 detergents were nominated as the cleaner that have the decontamination factor more than that of titanium dioxide paste.

Guideline for design and construction radiation monitoring equipments for Tokai reprocessing plant

Miyabe, Kenjiro; ; ;

JNC TN8410 2000-001, 159 Pages, 1999/12

JNC-TN8410-2000-001.pdf:4.0MB

Vorious kind of radiation monitoring equipment are used in radiation controlled area at each facility of Tokai reprocessing plant. These equipments have been designed and constructed based on the users requirements, and permitted by governmental regulation office. And, design has been carried out in consideration of the adoption of the new technology and our operational experience. Then, it has been used effectively for the radiation control of the facilities. This report summarizes the technical requirements that should be taken into consideration in the design and installation of radiation monitoring equipments. These requirements are fundamentally applicable when the equipments of the new facilities will be designed or the present instruments will be replaced.

None

Miyabe, Kenjiro; ; ; ;

JNC TN8440 99-028, 175 Pages, 1999/04

JNC-TN8440-99-028.pdf:13.68MB

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Miyabe, Kenjiro; ; Takasaki, Koji; ; Yasunaga, Hideo*; Izumi, Yuichi*

JNC TN8420 99-013, 110 Pages, 1999/04

JNC-TN8420-99-013.pdf:4.43MB

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Miyabe, Kenjiro; ; ; ; ; ;

PNC TN8440 98-038, 253 Pages, 1998/01

PNC-TN8440-98-038.pdf:7.96MB

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