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JAEA Reports

A Guide to introducing burnup credit, preliminary version (English translation)

Okuno, Hiroshi; Suyama, Kenya; Ryufuku, Susumu*

JAEA-Review 2017-010, 93 Pages, 2017/06

JAEA-Review-2017-010.pdf:2.47MB

There is an ongoing discussion on the application of burnup credit to the criticality safety controls of facilities that treat spent fuels. With regard to such application of burnup credit in Japan, this document summarizes the current technical status of the prediction of the isotopic composition and criticality of spent fuels, as well as safety evaluation concerns and the current status of legal affairs. This report is an English translation of A Guide to Introducing Burnup Credit, Preliminary Version, originally published in Japanese as JAERI-Tech 2001-055 by the Nuclear Fuel Cycle Facility Safety Research Committee.

JAEA Reports

SWAT3.1; The Integrated burnup code system driving continuous energy Monte Carlo codes MVP and MCNP

Suyama, Kenya; Mochizuki, Hiroki*; Takada, Tomoyuki*; Ryufuku, Susumu*; Okuno, Hiroshi; Murazaki, Minoru; Okubo, Kiyoshi

JAEA-Data/Code 2009-002, 124 Pages, 2009/05

JAEA-Data-Code-2009-002.pdf:14.09MB

Integrated burnup calculation code system SWAT is a system that combines neutronics calculation code SRAC widely used in Japan and point burnup calculation code ORIGEN2. It has been used to evaluate the composition of the uranium, plutonium, minor actinide and the fission products in the spent nuclear fuel. Because of the ability to treat the arbitrary fuel geometry and no requirement of generating the effective cross section data, there is a great advantage to introduce continuous energy Monte Carlo Code into the burnup calculation code. Based on this idea, the integrated burnup calculation code system SWAT3.1 was developed by combining the continuous energy Monte Carlo code MVP and MCNP and ORIGEN2. This report describes the outline, input data instruction and several example of the calculation.

Journal Articles

Revised data for 2nd version of Nuclear Criticality Safety Handbook/Data Collection

Okuno, Hiroshi; Ryufuku, Susumu*; Suyama, Kenya; Nomura, Yasushi; Tonoike, Kotaro; Miyoshi, Yoshinori

JAERI-Conf 2003-019, p.116 - 121, 2003/10

This paper outlines the data prepared for the 2nd version of Data Collection of the Nuclear Criticality Safety Handbook. These data are discussed in the order of its preliminary table of contents. The nuclear characteristic parameters (k$$_{rm inf}$$, M$$^{2}$$, D) were derived, and subcriticality judgment graphs were drawn for eleven kinds of fuels which were often encountered in criticality safety evaluation of fuel cycle facilities. For calculation of criticality data, benchmark calculations using the combination of the continuous energy Monte Carlo criticality code MVP and the Japanese Evaluated Nuclear Data Library JENDL-3.2 were made. The calculation errors were evaluated for this combination. The implementation of the experimental results obtained by using NUCEF facilities into the 2nd version of the Data Collection is under discussion. Therefore, related data were just mentioned. A database is being prepared to retrieve revised data easily.

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.

Oral presentation

Development of new general-purpose route-dose calculation code system

Yasuda, Hiroshi*; Sato, Tatsuhiko; Ryufuku, Susumu*; Matsuoka, Shungo*

no journal, , 

We developed a new general-purpose route-dose calculation code system. It enables us to estimate the aircrew doses on PC.

Oral presentation

Development of a data reduction software for iBIX

Ohara, Takashi; Kusaka, Katsuhiro*; Hosoya, Takaaki; Kurihara, Kazuo; Tomoyori, Katsuaki*; Niimura, Nobuo*; Tanaka, Ichiro*; Suzuki, Jiro*; Nakatani, Takeshi; Otomo, Toshiya*; et al.

no journal, , 

For a single crystal diffractometer, a data reduction software which extracts a HKLF list from the raw data is one of the most important components. We are now developing a new data reduction software for a new single crystal neutron diffractometer, "IBARAKI Biological Crystal Diffractometer (iBIX)", which is now constructing at the MLF of J-PARC.

Oral presentation

Development of a data processing software for a TOF single crystal neutron diffractometer at J-PARC

Ohara, Takashi; Kusaka, Katsuhiro*; Hosoya, Takaaki*; Kurihara, Kazuo; Tomoyori, Katsuaki*; Niimura, Nobuo*; Tanaka, Ichiro*; Suzuki, Jiro*; Nakatani, Takeshi; Otomo, Toshiya*; et al.

no journal, , 

no abstracts in English

Oral presentation

Quantitative evaluation on microstructural factors of cold rolled austenitic steels using neutron diffraction

Suzuki, Hiroshi; Saito, Toru; Tomota, Yo*; Suzuki, Tetsuya*; Xu, P.*; Ryufuku, Susumu*

no journal, , 

New method for evaluation of microstructural factors such as intergranular strain, texture, dislocation density and block size by superimposing on the texture contour map was developed. Using this method enable us to find out the deformation mechanism from these microstructural factors. Moreover comprehensive and complementary evaluations for these microstructural factors lead to clarifying the deformation and destruction mechanisms. The microstructural factors of high nitrogen SUS310 and SUS316 with 25% cold rolling were evaluated by this method. It was considered that difference of dislocation substructure between them probably caused the fact that the intergranular strain of SUS316 was higher than that of SUS310.

Oral presentation

Study on distribution and migration of radioactive substances around the Fukushima Daiichi Nuclear Power Plant; Development of prediction models for a local area

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

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Study on distribution and migration of radioactive substances around the Fukushima Daiichi Nuclear Power Plant; Measurements across the road and influence of snow cover

Sato, Satoshi; Kinase, Sakae; Saito, Kimiaki; Sakamoto, Ryuichi*; Ryufuku, Susumu*; Ishibashi, Kazufusa*

no journal, , 

no abstracts in English

Oral presentation

Study on distribution and migration of radioactive substances around the Fukushima Daiichi Nuclear Power Plant; Development of prediction models for a local area, 3; Ecological half-life evaluation

Ryufuku, Susumu*; Ishibashi, Kazufusa*; Hayashi, Hiroko*; Kurosawa, Naohiro*; Sato, Satoshi; Kinase, Sakae; Saito, Kimiaki; Takahashi, Tomoyuki*

no journal, , 

no abstracts in English

Oral presentation

Study on distribution and migration of radioactive substances around the Fukushima Daiichi Nuclear Power Plant, 9; Development of prediction models for distribution and migration of radioactive substances within 80 km of the Fukushima Daiichi Nuclear Power Plant

Kinase, Sakae; Takahashi, Tomoyuki*; Sato, Satoshi; Saito, Kimiaki; Kurosawa, Naohiro*; Ryufuku, Susumu*; Hayashi, Hiroko*; Ishibashi, Kazufusa*

no journal, , 

no abstracts in English

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