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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.

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

REIDAC; A Software package for retrospective dose assessment in internal contamination of radionuclides

Kurihara, Osamu; Hato, Shinji; Kanai, Katsuta; Takada, Chie; Takasaki, Koji; Ito, Kimio; Ikeda, Hiroshi*; Oeda, Mikihiro*; Kurosawa, Naohiro*; Fukutsu, Kumiko*; et al.

Journal of Nuclear Science and Technology, 44(10), p.1337 - 1346, 2007/10

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

In the case of internal contamination of radionuclides, it is necessary to perform internal dose assessment for radiation protection. For this purpose, the ICRP has given the dose coefficients and the retention and excretion rates for various radionuclides. However, these dosimetric quantities are calculated only in typical conditions, therefore, are not necessarily covered enough in the case of dose assessment in which specific information on the incident or/and individual biokinetic characteristics should be taken into account retrospectively. This paper describes a developed PC-based package of software REIDAC to meet the needs in retrospective dose assessment. REIDAC was verified by comparisons with dosimetric quantities given on the ICRP publications and several examples of practical use were also shown.

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

Development of dose assessment code for accidental tritium releases; ACUTRI

Yokoyama, Sumi; Noguchi, Hiroshi; Kurosawa, Naohiro*

Hoken Butsuri, 40(4), p.376 - 384, 2005/12

A computer code named ACUTRI has been developed to assess tritium doses due to inhalation to the general public. ACUTRI can calculate the radiological impact of tritium gas (HT) and tritiated water (HTO) released accidentally to the atmosphere. The models in this code consist of a tritium transfer model including the oxidation of HT to HTO and the reemission of HTO from soil to the atmosphere and a dose calculation model. The atmospheric dispersion of the primary HT and HTO plumes and secondary HTO plume, which is reemitted from soil to the atmosphere, is calculated by using the Gaussian plume model. In this calculation, it is possible to analyze statistically on meteorology in the same way as a conventional dose assessment method according to the meteorological guideline of the Nuclear Safety Commission of Japan. Tritium concentrations in air and their resultant doses were calculated using the ACUTRI code under some conditions. In order to validate the model, calculations were compared with experimental results.

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

Development of a code MOGRA for predicting the migration of ground additions and its application to various land utilization areas

Amano, Hikaru; Takahashi, Tomoyuki*; Uchida, Shigeo*; Matsuoka, Shungo*; Ikeda, Hiroshi*; Hayashi, Hiroko*; Kurosawa, Naohiro*

Journal of Nuclear Science and Technology, 40(11), p.975 - 979, 2003/11

 Times Cited Count:2 Percentile:79.95(Nuclear Science & Technology)

MOGRA is a migration prediction code for toxic ground additions including radioactive materials in a terrestrial environment. MOGRA consists of computational codes that are applicable to various evaluation target systems, and can be used on personal computers. The computational code has the dynamic compartment analysis block, GUI for computation parameter settings and results displays, data bases. The compartments are obtained by classifying various natural environments into groups that exhibit similar properties. A hypothetical combination of land usage was supposed to check the function of MOGRA. The land usage was consisted from cultivated lands, forests, uncultivated lands, urban area, river, and lake. Each land usage has its own inside model which is basic module. Also supposed was homogeneous contamination of the surface land from atmospheric deposition of $$^{137}$$Cs (1.0 Bq/m$$^{2}$$). The system analyzed the dynamic changes of $$^{137}$$Cs concentrations in each compartment, fluxes from one compartment to another compartment.

Journal Articles

MOGRA-DB; Database system for migration prediction code MOGRA

Amano, Hikaru; Ikeda, Hiroshi*; Sasaki, Toshihisa*; Matsuoka, Shungo*; Kurosawa, Naohiro*; Takahashi, Tomoyuki*; Uchida, Shigeo*

KEK Proceedings 2003-11, p.239 - 244, 2003/11

A Code MOGRA (Migration Of GRound Additions) is a migration prediction code for toxic ground additions including radioactive materials in a terrestrial environment, which consists of computational codes that are applicable to various evaluation target systems, and can be used on personal computers. The computational code has the dynamic compartment analysis block at its core, the graphical user interface (GUI) for model formation, computation parameter settings, and results displays. The code MOGRA has varieties of databases, which is called MOGRA-DB. Another additional code MOGRA-MAP can take in graphic map and calculate the square measure about the target land.

Journal Articles

Status of development of a code for predicting the migration of ground additions: MOGRA

Amano, Hikaru; Takahashi, Tomoyuki*; Uchida, Shigeo*; Matsuoka, Shungo*; Ikeda, Hiroshi*; Hayashi, Hiroko*; Kurosawa, Naohiro*

JAERI-Conf 2003-010, p.32 - 36, 2003/09

MOGRA (Migration Of GRound Additions) is a migration prediction code for toxic ground additions including radioactive materials in a terrestrial environment. MOGRA consists of computational codes that are applicable to various evaluation target systems, and can be used on personal computers. The computational code has the dynamic compartment analysis block at its core, the graphical user interface (GUI) for computation parameter settings and results displays, data files and so on. The compartments are obtained by classifying various natural environments into groups that exhibit similar properties. MOGRA has varieties of databases, which consist of radionuclides decay chart, distribution coefficients between solid and liquid, transfer factors from soil to plant, transfer coefficients from feed to beef and milk, concentration factors, and age dependent dose conversion factors for many radionuclides. Here the status of development of MOGRA is presented.

Journal Articles

Application of MOGRA for migration of contaminants through different land utilization areas

Amano, Hikaru; Takahashi, Tomoyuki*; Uchida, Shigeo*; Matsuoka, Shungo*; Ikeda, Hiroshi*; Hayashi, Hiroko*; Kurosawa, Naohiro*

JAERI-Conf 2003-010, p.112 - 121, 2003/09

The functionality of MOGRA is being verified by applying it in the analyses of the migration rates of radioactive substances from the atmosphere to soils and plants and flow rates into the rivers. This has been achieved by also taking their mode classifications into consideration. In this report, a hypothetical combination of land usage was supposed to check the function of MOGRA. The land usage was consisted from cultivated lands, forests, uncultivated lands, urban area, river, and lake. Each land usage has its own inside model which is basic module. Also supposed was homogeneous contamination of the surface land from atmospheric deposition of Cs-137 (1.0 Bq/m$$^{2}$$). The system can analyze the dynamic changes of Cs-137 concentrations in each compartment, fluxes from one compartment to another compartment.

Journal Articles

Equipment of model template for a code predicting the migration of ground additions, MOGRA

Takahashi, Tomoyuki*; Amano, Hikaru; Uchida, Shigeo*; Ikeda, Hiroshi*; Matsuoka, Shungo*; Hayashi, Hiroko*; Kurosawa, Naohiro*

Kankyo Eisei Kogaku Kenkyu, 17(3), p.340 - 344, 2003/07

no abstracts in English

JAEA Reports

ACUTRI: A Computer code for assessing doses to the general public due to acute tritium releases

Yokoyama, Sumi; Noguchi, Hiroshi; Ryufuku, Susumu*; Sasaki, Toshihisa*; Kurosawa, Naohiro*

JAERI-Data/Code 2002-022, 87 Pages, 2002/11

JAERI-Data-Code-2002-022.pdf:4.26MB

Tritium, which is used as a fuel of a D-T burning fusion reactor, is the most important radionuclide for the safety assessment of a nuclear fusion experimental reactor such as ITER. Thus, a computer code, ACUTRI, which calculates the radiological impact of tritium released accidentally to the atmosphere, has been developed, aiming to be of use in a discussion on licensing of a fusion experimental reactor and an environmental safety evaluation method in Japan. ACUTRI calculates an individual tritium dose based on transfer models specific to tritium in the environment. A Gaussian plume model is used for calculating the atmospheric dispersion of tritium gas (HT) and/or tritiated water (HTO). The environmental pathway model in ACUTRI considers the following internal exposures: inhalation from a primary plume (HT and/or HTO) released from the facilities and inhalation from a secondary plume (HTO) reemitted from the ground following deposition of HT and HTO. This report describes an outline of the ACUTRI code, a user guide and the results of test calculation.

Journal Articles

Environmental radiation dose information system used by cellular phones in JAERI

Tachibana, Haruo; Yamaguchi, Takenori; Matsuoka, Shungo*; Nemoto, Shintaro*; Kurosawa, Naohiro*

Proceedings of 1st Asian and Oceanic Congress for Radiation Protection (AOCRP-1) (CD-ROM), 7 Pages, 2002/10

An environmental radiation monitoring system in Tokai establishment of JAERI is composed of 14 monitoring posts, 4 monitoring stations, 2 drainage monitors and the monitoring data observation center. These monitoring posts and stations measure the gamma dose rate, and the monitoring stations measure the radioactive air concentration too. Drainage monitors measure the radioactive concentration in drain water. We developed the environmental radiation dose information system used by cellular phone for observing the monitoring data in day and night, working day and holiday at everyplace in Japan. This information system shows us the every minute or every 10 minutes monitoring data table and data trend graph on the cellular phone display. In the emergency situation, this system helps for speedy response such as the notification to the JAERI staffs, starting the emergency environmental monitoring activities, reporting the dose rate and concentration to the national and local authorities, and establishment of the emergency response team in JAERI.

Journal Articles

A Code for predicting the migration of ground additional MOGRA

Amano, Hikaru; *; Uchida, Shigeo*; Tsuzuki, Katsunori; Matsuoka, Shungo*; Ikeda, Hiroshi*; Matsubara, Takeshi*; Kurosawa, Naohiro*

KURRI-KR-80, p.48 - 49, 2001/12

no abstracts in English

JAEA Reports

Development of neutron and photon shielding calculation system for workstation (NPSS-W)

; Nojiri, Ichiro; Kurosawa, Naohiro*; *; Sasaki, Toshihisa*

PNC-TN8410 98-022, 145 Pages, 1998/01

PNC-TN8410-98-022.pdf:9.29MB

In plant designs and safety evaluations of nuclear fuel cycle facilities, it is important to evaluate the direct radiation and the skyshine (air-scattered photon radiation) from facilities reasonably. The Neutron and Photon Shielding Calculation System for Workstation (NPSS-W) was developed. The NPSS-W can carry out the shielding calculations of the photon and the neutron easily and rapidly. The NPSS-W can easily calculate the radiation source intensity by ORIGEN-S and the dose equivalent rate by S$$_{N}$$ transport calculational codes, which are ANISN and DOT3.5. The NPSS-W consists of five modules, which named CAL1, CAL2, CAL3, CAL4, CAL5). Some kinds of shielding calculational systems are calculated. The user's manual of NPSS-W the examples of calculations for each module and the output data are appended.

JAEA Reports

Development of PC version code system for radiation dose estimation

Harada, Yasunori; Sasamoto, Nobuo; Sakamoto, Yukio; Kurosawa, Naohiro*; *

JAERI-Data/Code 97-013, 196 Pages, 1997/03

JAERI-Data-Code-97-013.pdf:4.59MB

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

28 (Records 1-20 displayed on this page)