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JAEA Reports

Development of database of dose reduction factor for reducing equivalent doses to the thyroid by implementing iodine thyroid blocking (Contract research)

Kimura, Masanori; Munakata, Masahiro; Hato, Shinji*; Kanno, Mitsuhiro*

JAEA-Data/Code 2020-002, 38 Pages, 2020/03

JAEA-Data-Code-2020-002.pdf:3.23MB

To consider the method of implementing urgent protective actions in a nuclear accident appropriately, the authors have been assessing the effects of reducing doses by taking urgent protective actions using a Level 3 Probabilistic Risk Assessment (PRA) code, the OSCAAR, developed by the JAEA. Iodine thyroid blocking is an effective urgent protective action to reduce equivalent doses to the thyroid due to inhalation of radioactive iodine. However, the timing of the administration of stable iodine (SI) is important to maximize the effectiveness for thyroidal blocking. Therefore, the careful consideration should be given to the most effective way of iodine thyroid blocking when preparing off-site emergency plans. In the present study, the authors developed a new metabolic model for thyroid by combining the respiratory tract model (Publ.66) and gastrointestinal tract model (Publ.30) of the ICRP with a metabolic model for thyroid (Johnson's model) in order to calculate the behavior of radioiodine and stable iodine in the body more realistically. The model is useful to evaluate the effect of the administration of SI for reducing equivalent doses to the thyroid depending on the its timing. We also calculated the reduction factor for equivalent doses to the thyroid in order to the thyroid by using the model, and then developed the its database for the OSCAAR. Consequently, the OSCAAR can evaluate the effectiveness for thyroidal blocking realistically and promptly.

Journal Articles

Improvement of a metabolic model for iodine and consideration of a equivalent dose to the thyroid reduction factor for application to the OSCAAR code

Kimura, Masanori; Hato, Shinji*; Matsubara, Takeshi*; Kanno, Mitsuhiro*; Munakata, Masahiro

Proceedings of Asian Symposium on Risk Assessment and Management 2017 (ASRAM 2017) (USB Flash Drive), 9 Pages, 2017/11

The authors developed a new metabolic model for iodine by combining the respiratory tract model (Publ.66), the gastrointestinal tract model (Publ.30) of the ICRP and the metabolic model for iodine (Johnson's model) in order to evaluate the behavior of radioiodine and stable iodine in the body more realistically. The developed metabolic model indicated that a reduction factor (RF) depends on dosage of stable iodine, timing of the administration of stable iodine, different iodine isotopes ($$^{131}$$I - $$^{135}$$I), and age groups. Therefore, the RF was calculated by changing these parameters and then a database of the RF was constructed for the application to the OSCAAR code.

JAEA Reports

A Compartment model of radionuclide migration in environment based on exposure pathways

Kurikami, Hiroshi; Niizato, Tadafumi; Tsuruta, Tadahiko; Kato, Tomoko; Kitamura, Akihiro; Kanno, Mitsuhiro*; Kurosawa, Naohiro*

JAEA-Research 2016-020, 50 Pages, 2017/01

JAEA-Research-2016-020.pdf:6.02MB

In this report, we developed a compartment model of radionuclide migration in environment based on exposure pathways in a river basin scale and performed a preliminary calculation. The results showed good agreement with some measurement, although the comparison of bed sediment, transportation to outer sea and to agricultural products with the measurement was not enough. We continue to validate the model.

JAEA Reports

Design examination of the high-duty irradiation loop

Ogawa, Mitsuhiro; Iimura, Koichi; Hosokawa, Jinsaku; Kanno, Masaru

JAEA-Technology 2010-019, 178 Pages, 2010/07

JAEA-Technology-2010-019.pdf:20.16MB

JMTR is making preparations of the irradiation examinations towards the re-operation from the 2011 fiscal year now. Design examination of the high-duty irradiation loop is in one of these irradiation examinations of the irradiation plan. The examination is the plan to carry out the irradiation examination of the light water reactor fuel (uranium fuel and mixed oxide fuel) which reached the high burnup, under the irradiation environment nearer to the light water reactor plant. In the 2009 fiscal year, we carried out (1) System design and (2) Earthquake-proof calculation of in-pile tube of the high-duty irradiation loop. And, for the fuel action between covering pipe and pellets of fuel rod which reached the high burnup, we carried out (3) System design of the lift-off test facility. Moreover, we carried out (4) Examination about detection system of fuel breakage when a fuel sample is damaged, and (5) Examination about system composition of effluent treatment system.

Journal Articles

Development of calculation code for estimating radiation dose for hypothetical accident of nuclear facility considering radioactive decay chain during atmospheric dispersion of released radionuclides

Takeyasu, Masanori; Nakano, Masanao; Sumiya, Shuichi; Nemoto, Hiromi*; Kanno, Mitsuhiro*; Kurosawa, Naohiro*

Proceedings of 3rd Asian and Oceanic Congress on Radiation Protection (AOCRP-3) (CD-ROM), 4 Pages, 2010/05

The dose to the public at hypothetical accident of nuclear facility is estimated on the basis of the method described in the Japanese meteorological guideline. However, the radioactive decay during atmospheric dispersion of released radionuclide is not considered in the calculation formula in the guideline. Therefore, when the radionuclide of the half life such as a few min is released, the dose may be excessively over-estimated. In this study, the calculation code was developed which could consider the radioactive decay of the released radionuclide and the generation of the product. The dose calculated on the basis of the developed code was compared with that on the basis of the guideline.

JAEA Reports

Development of PASCLR code system version 2 to derive clearance levels of uranium and trans uranium wastes

Takeda, Seiji; Kanno, Mitsuhiro*; Sasaki, Toshihisa*; Minase, Naofumi*; Kimura, Hideo

JAEA-Data/Code 2006-003, 137 Pages, 2006/02

JAEA-Data-Code-2006-003.pdf:7.4MB

no abstracts in English

Journal Articles

Monte Carlo simulation of beta and $$gamma$$-rays emitted by radon progeny products in a thundercloud electric field and an analytical research on the atmospheric diffusion of the radon gases in the East Asia area

Torii, Tatsuo; Sugita, Takeshi*; Kido, Hiroko*; Kanno, Mitsuhiro*; Kurosawa, Naohiro*

Taiki Denki Kenkyu, (69), p.32 - 33, 2006/00

no abstracts in English

Journal Articles

Evaluation of clearance level of uranium and TRU waste

Kanno, Mitsuhiro*; Takeda, Seiji; Minase, Naofumi; Kato, Hideo; Kimura, Hideo

JAERI-Conf 2004-011, p.131 - 132, 2004/07

no abstracts in English

Journal Articles

Estimates of parameter and scenario uncertainties in shallow-land disposal of uranium wastes using deterministic and probabilistic safety assessment models

Takeda, Seiji; Kanno, Mitsuhiro; Minase, Naofumi; Kimura, Hideo

Journal of Nuclear Science and Technology, 39(8), p.929 - 937, 2002/08

no abstracts in English

Oral presentation

Analytical research on the atmospheric dispersion of the radon gases in East Asia area

Torii, Tatsuo; Kido, Hiroko*; Kanno, Mitsuhiro*; Kurosawa, Naohiro*

no journal, , 

A long-range model for advective diffusion of radon and its progeny products transported from the Asian continent was developed to investigate the effect of atmospheric radioactive substances to the winter thunderstorm. This system is based on regional meteorological model RAMS4.4 and material transport model HYPACT1.2. Using this system, a simulation was performed from October, 2002 to September, 2003. The annual fluctuation and advection from the continent were also studied.

Oral presentation

Simulation of the atmospheric transport of radon and its progenies in East Asia

Kido, Hiroko*; Torii, Tatsuo; Kanno, Mitsuhiro*; Kurosawa, Naohiro*

no journal, , 

no abstracts in English

Oral presentation

Study on distribution and migration of radioactive substances around the Fukushima Daiichi Nuclear Power Plant, 8; Characterization of monitoring data by vehicle-borne survey in local area

Sato, Satoshi; Kinase, Sakae; Saito, Kimiaki; Takahashi, Tomoyuki*; Kanno, Mitsuhiro*; Hayashi, Hiroko*; Ishibashi, Kazufusa*; Kurosawa, Naohiro*; Sakamoto, Ryuichi*; Nemoto, Hisashi*

no journal, , 

no abstracts in English

Oral presentation

Development and application of a compartment model for environmental fate of radioactive materials released from nuclear accidents

Kurikami, Hiroshi; Niizato, Tadafumi; Tsuruta, Tadahiko; Kato, Tomoko; Kitamura, Akihiro; Kanno, Mitsuhiro*; Kurosawa, Naohiro*

no journal, , 

To understand environmental fate of radioactive materials released from nuclear accidents is important for recovery measures. We have developed a compartment model including all important compartments and processes to describe environmental fate of radioactive materials and have applied to the Fukushima environment. The results showed a good agreement with field investigations.

14 (Records 1-14 displayed on this page)
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