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Journal Articles

Re-evaluation of radiation-energy transfer to an extraction solvent in a minor-actinide-separation process based on consideration of radiation permeability

Toigawa, Tomohiro; Tsubata, Yasuhiro; Kai, Takeshi; Furuta, Takuya; Kumagai, Yuta; Matsumura, Tatsuro

Solvent Extraction and Ion Exchange, 39(1), p.74 - 89, 2021/00

 Times Cited Count:0 Percentile:0(Chemistry, Multidisciplinary)

Absorbed-dose estimation is essential for evaluation of the radiation feasibility of minor-actinide-separation processes. We propose a dose-evaluation method based on radiation permeability, with comparisons of heterogeneous structures seen in the solvent-extraction process, such as emulsions forming in the mixture of the organic and aqueous phases. A demonstration of radiation-energy-transfer simulation is performed with a focus on the minor-actinide-recovery process from high-level liquid waste with the aid of the Monte Carlo radiation-transport code PHITS. The simulation results indicate that the dose absorbed by the extraction solvent from alpha ray depends upon the emulsion structure, and that from beta and gamma ray depends upon the mixer-settler-apparatus size. Non-negligible contributions of well-permeable gamma rays were indicated in terms of the plant operation of the minor-actinide-separation process.

Journal Articles

Measurements and evaluations of air dose rates around Fukushima, 2; Meanings and features of dose quantities used in radiation protection

Saito, Kimiaki; Yamamoto, Hideaki

Radioisotopes, 63(11), p.519 - 530, 2014/11

This article aims to provide the basic meanings and features of the doses frequently used in the measurements and evaluations of environmental radiation due to the Fukushima Dai-ichi Nuclear Power Plant accident. The following doses are explained and compared: absorbed dose as basic physical quantity; effective dose and equivalent dose for judgment in radiation protection; and ambient dose equivalent $$H^{*}$$(10) and individual dose equivalent $$H$$p(10) for radiation measurements.

Journal Articles

Development of three kinds of tissue substitutes for a physical phantom in neutron dosimetry

Tsuda, Shuichi; Endo, Akira; Yamaguchi, Yasuhiro

Journal of Nuclear Science and Technology, 42(10), p.877 - 887, 2005/10

 Times Cited Count:2 Percentile:18.81(Nuclear Science & Technology)

Three kinds of tissue substitutes were synthesized in order to develop a physical phantom for neutron dosimetry. The optimal elemental compositions and densities were determined using a Monte Carlo simulation method, based on absorbed dose distributions of neutrons of a few MeV in various materials. The characteristics of the synthesized tissue substitutes were verified by absorbed dose measurements using monoenergetic neutron sources and a $$^{252}$$Cf neutron source. It was found that the developed tissue substitutes, NAN-, HAI- and HONE-JAERI, have tissue equivalence to actual tissues within 10 % accuracy for neutrons in most of common fast neutron fields.

Journal Articles

Dose evaluation in criticality accident conditions using transient critical facilities fueled with a fissile solution

Nakamura, Takemi*; Tonoike, Kotaro; Miyoshi, Yoshinori

Radiation Protection Dosimetry, 110(1-4), p.483 - 486, 2004/09

 Times Cited Count:2 Percentile:17.98(Environmental Sciences)

Dose measurement and evaluation technique in criticality accident conditions with a thermo luminescence dosimeter (TLD) was studied at the Transient Experiment Critical Facility (TRACY) of Japan Atomic Energy Research Institute (JAERI). The tissue absorbed dose can be derived from the ambient dose equivalent given by measurement with a TLD using the conversion factor given by computation. Using this technique, the neutron dose around the SILENE reactor of the Institute for Radioprotection and Nuclear Safety (IRSN) of France was measured in the Accident Dosimetry Intercomparison Exercise (June 10-21, 2002) organized by OECD/NEA and IRSN. In this exercise, the $$gamma$$ dose was also measured with a TLD. In this report, measurements and evaluation results at TRACY and SILENE are presented.

JAEA Reports

Isopleths of surface air concentration and surface air kerma rate due to a radioactive cloud released from a stack, 3

Tachibana, Haruo; Kikuchi, Masamitsu; Sekita, Tsutomu; Yamaguchi, Takenori; Oeda, Mikihiro*; Kurosawa, Naohiro*

JAERI-Data/Code 2004-010, 19 Pages, 2004/06

JAERI-Data-Code-2004-010.pdf:1.92MB
JAERI-Data-Code-2004-010-appendix(CD-ROM).zip:12.12MB

This report is a revised edition of "Isopleths of Surface Air Concentration and Surface Air Absorbed Dose Rate due to a Radioactive Cloud Released from a Stack(II)"(JAERI-M 90-206) and based on the revised Nuclear Safety Guidelines reflected the ICRP1990 Recommendation. Characteristics of this report are the use of Air Karma Rate (Gy/h) unit instead of Air Absorbed Dose Rate (Gy/h) unit, and the records of isopleths of surface air concentration and surface air karma rate on CD-ROM. These recorded data on CD-ROM can be printed out on paper and/or pasted on digital map by personal computer.

Journal Articles

Energy dependence of absorbed dose distributions in a soft tissue substitute for neutron dosimetry

Tsuda, Shuichi; Endo, Akira; Yamaguchi, Yasuhiro

Journal of Nuclear Science and Technology, 41(Suppl.4), p.132 - 135, 2004/03

A solid material improved in hydrogen and oxygen contents was synthesized for development of a physical phantom for neutron. The elemental composition and density are aimed for those of the soft tissue in ICRU Report 44. The soft tissue equivalence has been verified by an absorbed dose measurement using a 252Cf neutron source. In the present work, absorbed doses were measured for the purpose of examinations of the characteristic of the synthesized soft tissue substitute for neutron of various energies, using mono-energetic 0.565 MeV neutrons from $$^{7}$$Li(p,n) reaction and 5 MeV from D(d,n) reaction, and quasi-mono-energetic ones (40 and 65 MeV) produced via $$^{7}$$Li(p,n) reaction. The measured absorbed doses were compared with those calculated by Monte Carlo simulation codes. The results indicate that the tissue substitute has a characteristic of soft tissue equivalence for neutron in the energy range from several hundred keV up to approximately 100 MeV.

Journal Articles

Synthesis and characterization of a soft-tissue substitute for neutron dosimetry

Tsuda, Shuichi; Endo, Akira; Yamaguchi, Yasuhiro

Journal of Nuclear Science and Technology, 40(12), p.1027 - 1031, 2003/12

 Times Cited Count:1 Percentile:11.39(Nuclear Science & Technology)

To develop a physical phantom for neutron dosimetry, a solid soft-tissue substitute was synthesized. The hydrogen and oxygen compositions of the synthesized tissue substitute, NAN-JAERI, are similar to those of the soft tissue in ICRU Report 44. To examine the radiation characteristics of the new soft-tissue substitute, absorbed dose distributions in NAN-JAERI were measured using a $$^{252}$$Cf neutron source. The measured absorbed dose distributions of neutrons and photons agree with those calculated by a Monte Carlo simulation code MCNP. The agreement between the experiment and the simulation verifies this method of evaluating the soft-tissue equivalence of NAN-JAERI for $$^{252}$$Cf neutrons. Similar simulations for some mono-energetic neutron sources showed that the newly developed tissue substitute has soft-tissue equivalent characteristics in the neutron energy range up to 14 MeV, in terms of the absorbed dose distributions in a slab phantom.

Journal Articles

Benchmark experiments for absorbed dose in a slab phantom for several tens MeV neutrons at the TIARA facility

Nakane, Yoshihiro; Sakamoto, Yukio

Proceedings of 5th Specialists' Meeting on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-5), p.241 - 252, 2000/00

no abstracts in English

Journal Articles

Characterization and performance study of high-dose $$^{60}$$Co $$gamma$$-ray calibration laboratory for radiation processing

Tachibana, Hiroyuki; Kojima, Takuji; ; ; Yotsumoto, Keiichi; Tanaka, Ryuichi

Radioisotopes, 48(4), p.247 - 256, 1999/04

no abstracts in English

Journal Articles

Uncertainty estimation in $$^{60}$$Co $$gamma$$-ray dosimetry at JAERI involving a two-way dose intercomparison study with NPL in the dose range 1-50kGy

Kojima, Takuji; Tachibana, Hiroyuki; ; *; P.H.G.Sharpe*

Radiation Physics and Chemistry, 54(6), p.619 - 626, 1999/00

 Times Cited Count:10 Percentile:62(Chemistry, Physical)

no abstracts in English

Journal Articles

Measurements of gamma dose rates in dwellings in the Tokyo metropolitan area

Saito, Kimiaki; Sakamoto, Ryuichi; Nagaoka, Toshi; Tsutsumi, Masahiro; Moriuchi, Shigeru*

Radiation Protection Dosimetry, 69(1), p.61 - 67, 1997/00

 Times Cited Count:13 Percentile:71.61(Environmental Sciences)

no abstracts in English

Journal Articles

$$gamma$$-ray dose intercomparison in the absorbed dose range, 5-50kGy, using dichromate and alanine dosimeters

H.H.Mai*; Ng.D.Duong*; Kojima, Takuji

Applied Radiation and Isotopes, 47(2), p.259 - 261, 1996/00

 Times Cited Count:2 Percentile:25.51(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Absorbed dose measurements and calculations in phantoms for 1.5 to 50keV photons

*; Tanaka, Shunichi; Nakane, Yoshihiro; Namito, Yoshihito*; Hirayama, Hideo*; Ban, Shuichi*;

Health Physics, 68(2), p.253 - 260, 1995/02

 Times Cited Count:9 Percentile:67.3(Environmental Sciences)

no abstracts in English

Journal Articles

Calibration of surveymeters for dose estimation with $$beta$$-ray sources simulating skin contamination

Yoshida, Makoto;

Hoken Butsuri, 28, p.187 - 193, 1993/00

no abstracts in English

JAEA Reports

Isopleths of surface air concentration and surface air absorbed dose rate due to a radioactive cloud released from a stack, II

Taki, Mitsumasa; Kobayashi, Hideo; Suzuki, Takashi; Shimizu, Isamu

JAERI-M 90-206, 345 Pages, 1990/11

JAERI-M-90-206.pdf:8.25MB

no abstracts in English

Journal Articles

Examination on conversion factors to estimate effective dose equivarent from absorbed dose in air for natural gamma radiations

Moriuchi, Shigeru; Tsutsumi, Masahiro; Saito, Kimiaki

Hoken Butsuri, 25, p.121 - 128, 1990/00

no abstracts in English

Journal Articles

Chemical dosimetry of mixed radiations in the FNS target room

Ikezoe, Yasumasa; ; Nakajima, Hayato; ;

Journal of Nuclear Science and Technology, 23(2), p.179 - 181, 1986/00

 Times Cited Count:1 Percentile:28.52(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Gamma-ray absorbed dose measurements in media with plural thermoluminescent dosimeters having different atomic numbers

;

Journal of Nuclear Science and Technology, 22(2), p.109 - 119, 1985/00

 Times Cited Count:13 Percentile:82.41(Nuclear Science & Technology)

no abstracts in English

32 (Records 1-20 displayed on this page)