Measurements and evaluations of air dose rates around the Fukushima NPP site, 6; Status and issues on evaluation of individual doses due to external exposures

Saito, Kimiaki; Kurihara, Osamu*; Matsuda, Norihiro; Takahara, Shogo; Sato, Tetsuro*

Radioisotopes, 65(2), p.93 - 112, 2016/02

https://doi.org/10.3769/radioisotopes.65.93

Late information is introduced on dose evaluation due to external exposures which employ an important role in the exposures due to the Fukushima accident. First, merits and demerits of the currently used two methods, that is the estimation based air dose rates and the measurements using personal dosimeters, are discussed indicating some basic data after a fundamental concept of external dose evaluation is provided. Next, main activities are summarized on external dose measurements and evaluations after the accident. Finally, a new trial on dose evaluation in introduced.

Dyed Polyvinyl Chloride films for use as high-dose routine dosimeters in radiation processing

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

Radiation Physics and Chemistry, 69(5), p.439 - 444, 2004/04

https://doi.org/10.1016/j.radphyschem.2003.08.006

Characteristics of the polyvinyl chloride films containing 0.11wt% of malachite green oxalate or 6GX-setoglausine with 100m in thickness were studied for use as routine dosimeters in radiation processing. These films show basically color bleaching under Co -ray irradiation in a dose range of 5 to 50 kGy. The sensitivity of the dosimeters and the linearity of dose response curves are improved by adding 2.5% of chloral hydrate [CClCH(OH)] and 0.15% hydroquinone [HOCHOH]. These additions extent the minimum dose limit to 1 kGy covering dosimetric quality assurance in radiation processing of food and healthcare products. The dose responses of both films at irradiation temperatures of 20-35C are constant relative to those at 25C, and the irradiation temperature coefficients for 35-55C were estimated to be (0.43 0.01)%/ C. The dosimeter characteristics are stable within 1% at 25C before and 60 days after irradiation.

Dose coefficients for radionuclides produced in high energy proton accelerator facilities; Coefficients for radionuclides not listed in ICRP publications

Kawai, Katsuo; Endo, Akira; Noguchi, Hiroshi

JAERI-Data/Code 2002-013, 66 Pages, 2002/05

JAERI-Data-Code-2002-013.pdf:2.75MB
JAERI-Data-Code-2002-013-DoseCD.pdf:81.85MB

Effective dose coefficients by inhalation and ingestion have been calculated for 334 nuclides, including (1) nuclides with half-lives 10min and their daughters that are not listed in ICRP Publications and (2) nuclides with half-lives 10min that are produced in a spallation target. Dose calculation was carried out using a nuclear decay database DECDC and a decay data library newly compiled from the ENSDF. The dose coefficients were calculated with the computer code DOCAP based on the respiratory tract model and biokinetic model of ICRP. The calculated results are presented as tables, which are the same forms as those in ICRP Publs.68 and 72. The complete listings of the dose coefficients are arranged on a CD-ROM, DoseCD, as indexed tables for inhalation of ten particle sizes, ingestion and injection into blood for workers and members of the public. The dose coefficients calculated in the present study are useful to calculate internal doses for a variety of radionuclides produced in high energy proton accelerator facilities.

Influence of pressure on cesium release from irradiated fuel at temperatures up to 2,773K

Kudo, Tamotsu; Hidaka, Akihide; Nakamura, Takehiko; Uetsuka, Hiroshi

Journal of Nuclear Science and Technology, 38(10), p.910 - 911, 2001/10

https://doi.org/10.3327/jnst.38.910

This article describes the effects of system pressure on the cesium release obtained in the first two tests of radionuclides release from irradiated fuel, VEGA-1 and VEGA-2, which were conducted at the same maximum temperature of 2773K and different system pressures. The fractional releases of Cs in VEGA-2 test at 1.0MPa were smaller than those in VEGA-1 test at atmospheric pressure. In order to quantify the difference of the release rate in the two tests due to the pressure, the release rate coefficients of Cs were evaluated. The Cs release rate coefficient in VEGA-2 was smaller by a factor of about 2.8 than that in VEGA-1 at temperature above about 1900K.

Dose coefficients for intakes of radionuclides by workers; Coefficients for radionuclides not listed in ICRP Publication 68

Endo, Akira; Yamaguchi, Yasuhiro

JAERI-Data/Code 99-047, p.24 - 0, 1999/12

JAERI-Data-Code-99-047.pdf:0.88MB

no abstracts in English

Estimation of HT gas diffusion coefficient and conversion rate constant of HT gas to HTO in intact soil

Murata, Mikio; Noguchi, Hiroshi

Nihon Genshiryoku Gakkai-Shi, 34(2), p.149 - 152, 1992/02

https://doi.org/10.3327/jaesj.34.149

no abstracts in English

Analysis of reactivity coefficients of the Chernobyl reactor by cell calculation

Tsuchihashi, Keichiro; Akino, Fujiyoshi

Journal of Nuclear Science and Technology, 24(12), p.1055 - 1065, 1987/12

https://doi.org/10.3327/jnst.24.1055

no abstracts in English

Diffusion-controlled tritium release from neutron-irradiated -LiAlO

;

Journal of Nuclear Materials, 138, p.210 - 214, 1986/00

https://doi.org/10.1016/0022-3115(86)90007-3

no abstracts in English

Measurements of Fission Products Released in Primary Cooling System of OWL-1 Loop

Yamamoto, Katsumune; Yokouchi, Iichiro; Okagawa, Seigo; ;

JAERI-M 83-007, 50 Pages, 1983/03

JAERI-M-83-007.pdf:1.65MB

no abstracts in English

Preliminary results of benchmark tests on JENDL-2

Kikuchi, Yasuyuki; Narita, Tsutomu;

Journal of Nuclear Science and Technology, 17(7), p.567 - 570, 1980/00

https://doi.org/10.3327/jnst.17.567

no abstracts in English