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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.

Journal Articles

Progress report of Japanese simulation research projects using the high-performance computer system Helios in the International Fusion Energy Research Centre

Ishizawa, Akihiro*; Idomura, Yasuhiro; Imadera, Kenji*; Kasuya, Naohiro*; Kanno, Ryutaro*; Satake, Shinsuke*; Tatsuno, Tomoya*; Nakata, Motoki*; Nunami, Masanori*; Maeyama, Shinya*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 92(3), p.157 - 210, 2016/03

The high-performance computer system Helios which is located at The Computational Simulation Centre (CSC) in The International Fusion Energy Research Centre (IFERC) started its operation in January 2012 under the Broader Approach (BA) agreement between Japan and the EU. The Helios system has been used for magnetised fusion related simulation studies in the EU and Japan and has kept high average usage rate. As a result, the Helios system has contributed to many research products in a wide range of research areas from core plasma physics to reactor material and reactor engineering. This project review gives a short catalogue of domestic simulation research projects. First, we outline the IFERC-CSC project. After that, shown are objectives of the research projects, numerical schemes used in simulation codes, obtained results and necessary computations in future.

JAEA Reports

Durability test of geomembrane liners presumed to avail near surface disposal facilities for Low-level waste generated from research, Industrial and Medical facilities

Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro; Kurosawa, Ryohei; Kanno, Naohiro*; Kashima, Takahiro*; Sakamoto, Yoshiaki

JAEA-Technology 2013-036, 47 Pages, 2014/02

JAEA-Technology-2013-036.pdf:5.27MB

The Low-level Radioactive Waste Disposal Project Center will construct near surface disposal facilities. The disposal facilities consist of concrete pit type for low-level radioactive wastes and trench type for very low level radioactive wastes. As for the trench type disposal facility, two kinds of facility designs are on projects -one for normal trench type disposal facilities and the other for trench type disposal facilities with geomembrane liners that could prevent from causing environmental effects of non radioactive toxic materials. This study examined mechanical strength and permeability properties to assess the durability on the basis of an indoor accelerated exposure experiment targeting the liner materials presumed to avail the conceptual design so far. Its results will be used for the basic and detailed design henceforth by confirming the empirical degradation characteristic with the progress of the exposure time.

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.

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

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.

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