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JAEA Reports

Development of deterministic approach to assess doses to the public from external exposures in the areas contaminated by the Fukushima Daiichi Nuclear Power Station Accident

Takahara, Shogo; Iijima, Masashi; Shimada, Kazumasa; Kushida, Teruo; Shiratori, Yoshitake

JAEA-Research 2014-024, 57 Pages, 2015/01

JAEA-Research-2014-024.pdf:5.49MB

In order to assess the doses to representative person using deterministic approach, we measured radiation dose rates and surveyed on behavioral patterns in the areas contaminated by the Fukushima Daiichi Nuclear Power Station Accident. Statistical analyzes were also performed to identify the characteristics of individual doses from external exposures, as well as radiation dose rates and behavioral patterns. Radiation dose rates measured in living areas distribute with lognormal form. Behavioral patterns of the populations were different corresponding to their occupation. Time spent outdoors of indoor workers were distributed in lognormal form and those of outdoor workers had the normal distribution. Multi-regression analyses were made to explore a significant relationship between individual doses and relevant contributors. These results indicated that the significant differences were given in individual doses due to the spatial differences of radiation dose rates as well as the interindividual differences of behavioral patterns. Based on the results of analyses of relevant contributors to the external exposures, deterministic dose assessment model was developed. The validity of this model was confirmed because the assessed values were higher than those measured.

Journal Articles

Statistical characterization of radiation doses from external exposures and relevant contributors in Fukushima Prefecture

Takahara, Shogo; Abe, Tatsuya*; Iijima, Masashi; Shimada, Kazumasa; Shiratori, Yoshitake

Health Physics, 107(4), p.326 - 335, 2014/10

AA2013-0905.pdf:0.46MB

 Times Cited Count:8 Percentile:53.55(Environmental Sciences)

Probabilistic dose assessment is one of the useful methods to describe the information on the dose distributions in the population. To use this assessment, statistically characterized data on the pathway-relevant contributors are necessary. The objectives of the paper are to determine the statistical values and the distribution forms of the contributors to external exposures, as well as to identify the causes of the variabilities of them. To achieve the objectives, we have measured and surveyed ambient dose rate and time spent outdoors in Fukushima Prefecture. The measurements and surveys were performed with the cooperation of indoor workers, outdoor workers and pensioners. These results allowed us to determine the statistically characters of the individual doses and its contributors. In addition, these contributors had the variabilities attributed to the spatial distributions of deposited radionuclides, as well as the temporal and interpopulational differences of behavioral patterns.

JAEA Reports

Decontamination pilot projects for the environmental remediation of evacuation areas contaminated with radioactive materials discharged from the Fukushima Daiichi Nuclear Power Plant accident; Survey on individual doses to the inhabitants living in the areas contaminated by the accident (Contract research)

Takahara, Shogo; Iijima, Masashi; Kushida, Teruo; Shiratori, Yoshitake

JAEA-Research 2013-029, 36 Pages, 2013/12

JAEA-Research-2013-029.pdf:2.7MB

In the areas contaminated by the Fukushima Daiichi Nuclear Power Plant accident, to clarify the influences of the lifestyle habits to radiation exposures for inhabitants, we performed surveys on their behavioral patterns and measurements of their individual doses due to external exposures. In addition, an assessment model was developed and the assessments of the doses were performed based on the results of the surveys and the measurements of ambient dose equivalent rates. The assessed individual doses were compared with those measured in order to confirm the validity of the model. Clear differences were found in time spent outdoors of the inhabitants of various occupations. Significant differences in individual doses were also observed between those of indoor workers and outdoor workers. In order to assess more precisely the doses of inhabitants who continue to live in the affected areas, assessments should be performed taking into account the population-specific behavioral patterns.

Journal Articles

Analysis of Mixed Oxide Fuel Loaded Cores in the Heavy Water Reactor FUGEN

Otani, Tsukasa; Iijima, Takashi; Shiratori, Yoshitake

Journal of Nuclear Science and Technology, 40(11), p.959 - 969, 2003/11

 Times Cited Count:5 Percentile:36.82(Nuclear Science & Technology)

None

Journal Articles

Preparatory Activities for Reducing Exposure Dosage during Fugen Decommissioning Project

; Iguchi, Yukihiro; Kanehia, Yoshiki; Shiratori, Yoshitake;

Hoken Butsuri, 38(2), p.116 - 127, 2003/06

None

Journal Articles

Radiation activity evaluation for decommissioning of Fugen Nuclear Power Station

Shiratori, Yoshitake; ; Higashiura, Norikazu

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 0 Pages, 2003/00

None

JAEA Reports

Measured result of ATR fuel power distribution by $$gamma$$-scanning apparatus

Shiratori, Yoshitake; Nagamatsu, Kenji; Ozaki, Shinji; Hayashi, Takashi

PNC TN3410 92-016, 7 Pages, 1992/12

PNC-TN3410-92-016.pdf:0.2MB

None

JAEA Reports

Operation experience of MOX fuel loaded heavy water reactor

Shiratori, Yoshitake; Furubayashi, Toshiyuki; Matsumoto, Mitsuo

PNC TN3410 91-031, 47 Pages, 1991/11

ugen has been operating safely and smoothly for twelve years using mainly plutonium-uranium mixed oxide (mox) fuels, and much operation data has been accumulated during this time. Fugen's core management has been established, and its core characteristics have been evaluated through the operation. the effect of $$^{241}$$am accumulation and plutonium composition ratio must be considered when many mox fuels are used in a thermal reactor. Calculation accuracy of core analysis code is good and core characteristics are well evaluated by the consideration of these factors. Fuel inspection shows that there is no big difference between mox and uo$$_{2}$$ fuel.

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