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JAEA Reports

Development of software tools for 4-D visualization and quantitative analysis of PHITS simulation results

Furutaka, Kazuyoshi

JAEA-Data/Code 2014-027, 32 Pages, 2015/02

JAEA-Data-Code-2014-027.pdf:7.25MB

A suite of software tools has been developed to facilitate the development of apparatus using a radiation transport simulation code PHITS by enabling 4D visualization (3D space and time) and quantitative analysis of so-called dieaway plots. To deliver useable tools as soon as possible, the existing software was utilized as much as possible; ParaView will be used for the 4D visualization of the results, whereas the analyses of dieaway plots will be done with ROOT toolkit with a tool named "diana". To enable 4D visualization using ParaView, a suite of tools (angel2vtk, DispDCAS1, CamPos) have been developed for the conversion of the data format to the one which can be read from ParaView and to ease the visualization.

Journal Articles

Accessibility evaluation of the IFMIF liquid lithium loop considering activated erosion/corrosion materials deposition

Nakamura, Hiroo; Takemura, Morio*; Yamauchi, Michinori*; Fischer, U.*; Ida, Mizuho*; Mori, Seiji*; Nishitani, Takeo; Simakov, S.*; Sugimoto, Masayoshi

Fusion Engineering and Design, 75-79, p.1169 - 1172, 2005/11

 Times Cited Count:5 Percentile:36.91(Nuclear Science & Technology)

In the IFMIF, activated erosion/corrosion materials of Li target back wall deposits on a surface of the Li loop. Therefore, accessibility during maintenance of the Li loop pipings will depend on the activation level of the deposition materials. This paper evaluates effect of target activation on the accessibility of the Li loop pipings. Activation level is calculated by the ACT-4 code. High energy cross section above 15 MeV is introduced using IEAF-2001 data. In this calculation, target material is stainless steel 316. Area of the erosion/corrosion in the back wall is 100 cm$$^{2}$$. The erosion/corrosion rate is 1 micron/y. Dose rate around the Li loop after one year IFMIF operation is evaluated assuming 1% deposition of the erosion/corrosion materials and uniform deposition on surface area of 33 m$$^{2}$$. Permissible level for hands-on maintenance is 10 microSv/hr. As the results, after 1 week from shutdown, close maintenance work 8 cm to the Li loop is possible. Also, after 1 month, hands-on maintenance becomes possible.

Journal Articles

Estimation of radioactivities in the IFMIF liquid lithium loop due to the erosion and corrosion of target back-wall

Yamauchi, Michinori*; Takemura, Morio*; Nakamura, Hiroo; Fischer, U.*; Ida, Mizuho*; Mori, Seiji*; Sato, Satoshi; Nishitani, Takeo; Simakov, S. P.*; Sugimoto, Masayoshi

Fusion Science and Technology, 47(4), p.1008 - 1011, 2005/05

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Present status of beryllide R&D as neutron multiplier

Kawamura, Hiroshi; Takahashi, Heishichiro*; Yoshida, Naoaki*; Mishima, Yoshinao*; Ishida, Kiyohito*; Iwadachi, Takaharu*; Cardella, A.*; Van der Laan, J. G.*; Uchida, Munenori*; Munakata, Kenzo*; et al.

Journal of Nuclear Materials, 329-333(1), p.112 - 118, 2004/08

 Times Cited Count:31 Percentile:87.63(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

6th IEA International Workshop on Beryllium Technology for Fusion(BeWS-6)

Kawamura, Hiroshi; Tanaka, Satoru*; Ishitsuka, Etsuo

Nihon Genshiryoku Gakkai-Shi, 46(8), p.578 - 579, 2004/08

IEA 6th International Workshop on Beryllium Technology for Fusion(BeWS-6) was held at World Convention Center SUMMIT, Miyazaki city from Dec.2 2004 to Dec.5 2004. This is an outline of meeting report of BeWS-6.

JAEA Reports

IFMIF-KEP; International Fusion Materials Irradiation Facility key element technology phase report

IFMIF International Team

JAERI-Tech 2003-005, 559 Pages, 2003/03

JAERI-Tech-2003-005.pdf:48.89MB

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m$$^{2}$$, 20 dpa/y in Fe, in a volume of 500 cm$$^{3}$$ and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration.

JAEA Reports

Report of IEA Workshop on Reduced Activation Ferritic/Martensitic Steels; November 2-3, 2000, Tokyo, Japan

Department of Fusion Engineering Research; Department of Materials Science

JAERI-Conf 2001-007, 526 Pages, 2001/03

JAERI-Conf-2001-007.pdf:71.57MB

no abstracts in English

Journal Articles

Effective thermal conductivity measurement of the candidate ceramic breeder pebble beds by the hot wire method

Enoeda, Mikio; Ohara, Yoshihiro; Roux, N.*; Ying, A.*; Pizza, J.*; Malang, J.*

Fusion Technology, 39(No.2 Part.2), p.612 - 616, 2001/03

no abstracts in English

Journal Articles

Experimental test of structural materials activation in the IFMIF neutron spectrum

Von-Moellendorff, U.*; Maekawa, Fujio; Giese, H.*; Wilson, P. P. H.*

Fusion Engineering and Design, 51-52(Part.B), p.919 - 924, 2000/11

 Times Cited Count:4 Percentile:33.22(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of spark plasma sintering (SPS) joining technique for reduced activation ferritic steel F-82H

; Shiba, Kiyoyuki; Hishinuma, Akimichi

JAERI-Tech 97-061, 46 Pages, 1997/11

JAERI-Tech-97-061.pdf:5.39MB

no abstracts in English

JAEA Reports

Properties of low activation ferritic steel F82H IEA heat; Interim report of IEA round-robin tests, 1

Shiba, Kiyoyuki; Hishinuma, Akimichi; *; *

JAERI-Tech 97-038, 110 Pages, 1997/08

JAERI-Tech-97-038.pdf:5.13MB

no abstracts in English

JAEA Reports

Addendum to IFMIF-CDA interim report

JAERI-Tech 96-036, 32 Pages, 1996/08

JAERI-Tech-96-036.pdf:1.27MB

no abstracts in English

Journal Articles

Present status of fusion reactor materials database promoted by International Energy Agency(IEA)

Nakajima, Hajime

Kaku Yugoro Zairyo Foramu, 6, p.123 - 136, 1992/00

no abstracts in English

Journal Articles

IEA Workshop on In-Situ Measurements of Electrical Properties of Irradiated Ceramics

Ono, Hideo

Nihon Genshiryoku Gakkai-Shi, 32(11), p.1099 - 1100, 1990/11

no abstracts in English

Journal Articles

Outline of IEA Energy Technology Data Exchange Program

Nihon Genshiryoku Gakkai-Shi, 30(3), p.207 - 211, 1988/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evolution of the Japanese test coil work for the large coil task

; ; Hiyama, Tadao; ; ; ; ; ; ; ; et al.

IEEE Transactions on Magnetics, 17(5), p.1734 - 1737, 1981/00

no abstracts in English

Journal Articles

Analysis of dieaway experiments in a uranium-238 sphere

Journal of Nuclear Science and Technology, 10(10), p.619 - 625, 1973/10

no abstracts in English

19 (Records 1-19 displayed on this page)
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