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Nakamura, Hideo; Bentaib, A.*; Herranz, L. E.*; Ruyer, P.*; Mascari, F.*; Jacquemain, D.*; Adorni, M.*
Proceedings of International Conference on Topical Issues in Nuclear Installation Safety; Strengthening Safety of Evolutionary and Innovative Reactor Designs (TIC 2022) (Internet), 10 Pages, 2022/10
Uwaba, Tomoyuki; Nemoto, Junichi*; Ito, Masahiro*; Ishitani, Ikuo*; Doda, Norihiro; Tanaka, Masaaki; Otsuka, Satoshi
Nuclear Technology, 207(8), p.1280 - 1289, 2021/08
Times Cited Count：3 Percentile：35.51(Nuclear Science & Technology)Computer codes for irradiation behavior analysis of a fuel pin and a fuel pin bundle and for coolant thermal hydraulics analysis were coupled into an integrated code system. In the system, each code provides data required by other codes and the analyzed results are shared among them. The system allows for the synthesizing of analyses of thermal, chemical and mechanical behaviors in a fuel subassembly under irradiation. A test analysis was made for a fuel subassembly containing a mixed oxide fuel pin bundle irradiated in a fast reactor. The results of the analysis were presented with transverse cross-sectional images of the fuel subassembly and three-dimensional images of a fuel pin and fuel pin bundle models. For detailed evaluation, various irradiation behaviors of all fuel pins in the subassembly were analyzed and correlated with irradiation conditions.
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.
Kunieda, Satoshi; Ichihara, Akira
JAERI-Data/Code 2005-005, 33 Pages, 2005/09
JAERI-Data-Code-2005-005.pdf:1.5MB
The computer code, POD-P, was developed to calculate energy spectra and angular distributions of emitted particles for the neutron-induced preequiliblium nuclear reactions. The energy-differential cross sections are computed with the classical one-component exciton model for the nucleon and composite-particle emissions. Along with this, the semi-empirical exciton models are also used for the composite-particle emissions. The double-differential cross sections are derived from those model calculations plus the angular-distribution systematics. The computational method and explanation of input parameters are given with some output examples.
Ichihara, Akira; Kunieda, Satoshi; Chiba, Satoshi; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Fukahori, Tokio; Katakura, Junichi
JAERI-Data/Code 2005-004, 54 Pages, 2005/07
JAERI-Data-Code-2005-004.pdf:1.63MB
The computer code, POD, was developed to calculate angle-differential cross sections and analyzing powers for shape-elastic scattering for collisions of neutron or light ions with target nucleus. The cross sections are computed with the optical model. Angle-differential cross sections for neutron inelastic scattering can also be calculated with the distorted-wave Born approximation. The optical model potential parameters are the most essential inputs for those model computations. The cross sections and analyzing powers are obtained by using the existing local or global parameters. The parameters can also be inputted by users. In this report, the theoretical formulas, the computational methods, and the input parameters are explained. The sample inputs and outputs are also presented.
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.
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.
Suzuki, Mitsuhiro
JAERI-Tech 2002-071, 171 Pages, 2002/10
JAERI-Tech-2002-071.pdf:11.26MB
no abstracts in English
Kumada, Hiroaki; Torii, Yoshiya
JAERI-Data/Code 2002-018, 158 Pages, 2002/09
JAERI-Data-Code-2002-018.pdf:30.28MB
A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimentional head model of a patient by using CT and MRI images and that generates a input data file automaticly for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patinet's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal for the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System to set the patient in an actual irradiation position swiftly and accurately. This report describes basic design and procedure of dosimetry, operation manual, data and library structure for JCDS (ver.1.0)
Kobayashi, Takuya; Togawa, Orihiko; Odano, Naoteru; Ishida, Toshihisa
Journal of Nuclear Science and Technology, 38(8), p.658 - 663, 2001/08
Times Cited Count：2 Percentile：19.66(Nuclear Science & Technology)The collective dose to the Japanese population has been estimated from a hypothetical accident of a nuclear submarine if it sinks in an offshore region around Japan. A computer code system DSOCEAN has been used for assessing the collective dose due to radionuclides released to the ocean from a sunken nuclear submarine. The maximum of the estimated collective effective dose equivalent by the annual intake of marine products after radionuclide releases for one year is approximately 0.5% of the annual average dose by the natural radiation that is reported by UNSCEAR.
Takahashi, Tomoyuki*; Takeda, Seiji; Kimura, Hideo
JAERI-Data/Code 2000-041, 108 Pages, 2001/01
JAERI-Data-Code-2000-041.pdf:4.86MB
no abstracts in English
Komuro, Yuichi
Nihon Genshiryoku Gakkai-Shi, 42(12), p.1301 - 1310, 2000/12
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Murata, Mikio*; Noguchi, Hiroshi; Yokoyama, Sumi*
JAERI-Data/Code 2000-034, 214 Pages, 2000/11
JAERI-Data-Code-2000-034.pdf:7.43MB
no abstracts in English
Shimakawa, Satoshi; Tabata, Toshio; Komukai, Bunsaku
JAERI-Data/Code 99-045, p.31 - 0, 1999/11
JAERI-Data-Code-99-045.pdf:1.22MB
no abstracts in English
Togawa, Orihiko; Homma, Toshimitsu; Masumura, Tomomi*
JAERI-Data/Code 99-002, 59 Pages, 1999/01
JAERI-Data-Code-99-002.pdf:2.55MB
no abstracts in English
T.V.Hung*; Sakamoto, Yukio; Yasuda, Hideshi
JAERI-Research 98-057, 25 Pages, 1998/10
JAERI-Research-98-057.pdf:1.04MB
no abstracts in English
Okumura, Keisuke
JAERI-Data/Code 98-025, 243 Pages, 1998/10
JAERI-Data-Code-98-025.pdf:10.15MB
no abstracts in English
Kugo, Teruhiko; Nakakawa, Masayuki;
Journal of Nuclear Science and Technology, 34(8), p.760 - 770, 1997/08
Times Cited Count：2 Percentile：23.04(Nuclear Science & Technology)no abstracts in English
Murao, Yoshio
Konsoryu, 11(3), p.203 - 204, 1997/00
no abstracts in English
Kukita, Yutaka*; Arai, Kenji*; *
Nihon Genshiryoku Gakkai-Shi, 39(2), p.151 - 153, 1997/00
no abstracts in English
