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Journal Articles

Analysis on the co-localization of asbestos bodies and Fas or CD163 expression in asbestos lung tissue by in-air micro-PIXE

Dobashi, Kunio*; Shimizu, Yasuo*; Matsuzaki, Shinichi*; Nagamine, Takeaki*; Sato, Takahiro; Okubo, Takeru; Yokoyama, Akihito; Ishii, Yasuyuki; Kamiya, Tomihiro; Arakawa, Kazuo*; et al.

JAEA-Review 2011-043, JAEA Takasaki Annual Report 2010, P. 87, 2012/01

Journal Articles

COMPASS code development; Validation of multi-physics analysis using particle method for core disruptive accidents in sodium-cooled fast reactors

Koshizuka, Seiichi*; Morita, Koji*; Arima, Tatsumi*; Tobita, Yoshiharu; Yamano, Hidemasa; Ito, Takahiro*; Naito, Masanori*; Shirakawa, Noriyuki*; Okada, Hidetoshi*; Uehara, Yasushi*; et al.

Proceedings of 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8) (CD-ROM), 11 Pages, 2010/10

In this paper, FY2009 results of the COMPASS code development are reported. Validation calculations for melt freezing and blockage formation, eutectic reaction of metal fuel, duct wall failure (thermal-hydraulic analysis), fuel pin failure and disruption and duct wall failure (structural analysis) are shown. Phase diagram calculations, classical and first-principles molecular dynamics were used to investigate physical properties of eutectic reactions: metallic fuel/steel and control rod material/steel. Basic studies for the particle method and SIMMER code calculations supported the COMPASS code development. COMPASS is expected to clarify the basis of experimentally-obtained correlations used in SIMMER. Combination of SIMMER and COMPASS will be useful for safety assessment of CDAs as well as optimization of the core design.

Journal Articles

J-PARC muon facility, MUSE

Miyake, Yasuhiro*; Shimomura, Koichiro*; Kawamura, Naritoshi*; Strasser, P.*; Makimura, Shunsuke*; Koda, Akihiro*; Fujimori, Hiroshi*; Nakahara, Kazutaka*; Takeshita, Soshi*; Kobayashi, Yasuo*; et al.

Journal of Physics; Conference Series, 225, p.012036_1 - 012036_7, 2010/06

 Times Cited Count:7 Percentile:91.45

Journal Articles

Analysis on the Co-localization of asbestos bodies and Fas or CD163 expression in asbestos lung tissue by in-air micro-PIXE

Matsuzaki, Shinichi*; Shimizu, Yasuo*; Dobashi, Kunio*; Nagamine, Takeaki*; Sato, Takahiro; Okubo, Takeru; Yokoyama, Akihito; Ishii, Yasuyuki; Kamiya, Tomihiro; Arakawa, Kazuo*; et al.

International Journal of Immunopathology and Pharmacology, 23(1), p.1 - 11, 2010/01

Journal Articles

Validation for multi-physics simulation of core disruptive accidents in sodium-cooled fast reactors by COMPASS code

Koshizuka, Seiichi*; Morita, Koji*; Arima, Tatsumi*; Zhang, S.*; Tobita, Yoshiharu; Yamano, Hidemasa; Ito, Takahiro*; Naito, Masanori*; Shirakawa, Noriyuki*; Okada, Hidetoshi*; et al.

Proceedings of 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13) (CD-ROM), 11 Pages, 2009/09

Dispersion and freezing of molten core material was calculated by the COMPASS code to compare with the experimental data of GEYSER. Molten core material flowed up with freezing on the pipe inner surface. As a molten pool behavior, CABRI-TPA2 experiment was analyzed, where a sphere of solid steel was surrounded by solid fuel. Power was injected to cause melting and boiling of the steel sphere. SCARABEE-BE+3 test was analyzed by COMPASS as a validation of failure of duct walls.

JAEA Reports

Post irradiation examination results of MA containing MOX fuel; Non-destructive examination results of the fuel pins

Ishimi, Akihiro; Katsuyama, Kozo; Abe, Kazuyuki; Nagamine, Tsuyoshi; Nakamura, Yasuo

JAEA-Technology 2009-003, 58 Pages, 2009/05

JAEA-Technology-2009-003.pdf:8.95MB

Japan Atomic Energy Agency executed the irradiation examination of the MA content mixed oxide fuel by Experimental Fast Reactor "JOYO". This examination was used that the mixed oxide fuel that contained Americium by 3% and 5%, and the mixed oxide fuel of Americium and Neptunium that contained 2% for each. The irradiation examination executed a short term irradiation (For ten minutes and 24 hours) by the high linear heat, and achieved maximum linear heat about 430 W/cm in "JOYO". After it had irradiated it, the post irradiation examination of the fuel pin was executed in the Fuels Monitoring facilities. On the results of X ray CT examination, the result that the density decrease is forecast to the vicinity of the center of the fuel was obtained for ten minutes in the irradiation. The formation of the central void was confirmed to the center of the fuel in 24 hour irradiation.

Journal Articles

Code development for multi-physics and multi-scale analysis of core disruptive accidents in fast reactors using particle methods

Koshizuka, Seiichi*; Morita, Koji*; Arima, Tatsumi*; Zhang, S.*; Tobita, Yoshiharu; Yamano, Hidemasa; Ito, Takahiro*; Shirakawa, Noriyuki*; Naito, Masanori*; Okada, Hidetoshi*; et al.

Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 6 Pages, 2008/10

A computer code, named COMPASS, is being developed for various complex phenomena of core disruptive accidents (CDAs) in sodium-cooled fast reactors (SFRs). The COMPASS is designed to analyze multi-physics problems involving thermal hydraulics, structure and phase change, in a unified framework of the MPS (Moving Particle Semi-implicit) method. The project has been carried out by six organizations for five years from FY2005 to FY2009. In this paper, the outcomes of the project in FY2007 are presented. Three validation calculations were completed by following the validation plan: melt freezing and blockage formation, molten pool boiling, and duct wall failure. The COMPASS code development was supported by basic studies of the numerical method, material science for eutectic reaction of the metal fuel, and SIMMER-III analyses.

JAEA Reports

Re-assembly technology establishment of Material Testing Rig with Temperature Control (MARICO-2)

Abe, Kazuyuki; Kobayashi, Takashi*; Kajima, Hisashi*; Yoshikawa, Katsunori; Nagamine, Tsuyoshi; Nakamura, Yasuo

JAEA-Technology 2008-008, 53 Pages, 2008/03

JAEA-Technology-2008-008.pdf:19.28MB

MARICO-2 is a Testing Rig for the continuous irradiation examination of ODS ferrite steel etc.. It was necessary to re-assemble of MARICO-2 in Fuel Monitoring Facility (FMF). However, MARICO-2 is not applicable a past technology of re-assembly because it is a Rig of the total length about 11 m and its hex-tube must be welded by remote control. Then, MARICO-2 re-assembly technology development was executed, the device was designed, it produced, and the procedure of re-assembly by remote control was established.

Journal Articles

Three-dimensional X-ray CT image of irradiated FBR fuel assembly

Katsuyama, Kozo; Nagamine, Tsuyoshi; Nakamura, Yasuo; Asaka, Takeo; Furuya, Hirotaka

Transactions of the American Nuclear Society, 97(1), p.620 - 621, 2007/11

no abstracts in English

Journal Articles

Development of design technology on thermal-hydraulic performance in tight-lattice rod bundle, 3; Numerical estimation on rod bowing effect based on X-ray CT data

Misawa, Takeharu; Onuki, Akira; Mitsutake, Toru*; Katsuyama, Kozo; Misawa, Susumu*; Nagamine, Tsuyoshi; Nakamura, Yasuo; Akimoto, Hajime

Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 8 Pages, 2007/04

Journal Articles

Measurement of the fuel pin deflection in an assembly irradiated in FBR "JOYO"

Katsuyama, Kozo; Nagamine, Tsuyoshi; Nakamura, Yasuo; Matsumoto, Shinichiro; Asaka, Takeo; Furuya, Hirotaka

Transactions of the American Nuclear Society, 94(1), p.771 - 772, 2006/06

no abstracts in English

Oral presentation

Establishment of the re-assembling technology of the irradiation rig with a Welding by remote control

Abe, Kazuyuki; Kobayashi, Takashi*; Kajima, Hisashi*; Nagamine, Tsuyoshi; Nakamura, Yasuo

no journal, , 

To clarify behavior of the material and fuel of the fast reactor under high burn-up and the high fluence, re-assembly of "JOYO" irradiation rig is executed in Japan Atomic Energy Agency. This time, the re-assembling technology with a welding was established, newly. This technology is an upgrade of the continuance irradiation technology further for clear of the irradiation behavior of the fuel and the material.

Oral presentation

Development of eddy current testing technique for fast reactor fuel pins; ECT results of irradiated fuel pins

Miyaji, Noriko; Katsuyama, Kozo; Nagamine, Tsuyoshi; Nakamura, Yasuo; Otani, Akira*

no journal, , 

no abstracts in English

Oral presentation

Measurement of fuel pin displacement in fuel assembly for fast reactor

Katsuyama, Kozo; Nagamine, Tsuyoshi; Nakamura, Yasuo; Misawa, Susumu*

no journal, , 

no abstracts in English

Oral presentation

Helium gas release behavior of FBR MOX fuel containing $$^{241}$$Am

Katsuyama, Kozo; Nagamine, Tsuyoshi; Nakamura, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Development of a non-destructive post-irradiation examination technique using high-energy X-ray computer tomography

Katsuyama, Kozo; Nagamine, Tsuyoshi; Nakamura, Yasuo

no journal, , 

High-energy X-ray computer tomography (X-ray CT) is one of the most powerful non-destructive test tools for checking the inner condition of structure materials. This technique has been applied to the inspection of structure materials such as the booster rocket and the engine of automobile. However, the application of X-ray CT technique to the post irradiation examination (PIE) of nuclear reactor fuel was impossible due to the effects of $$gamma$$ ray emissions from an irradiated fuel assembly. In order to minimize the effects of the $$gamma$$ ray emissions from the irradiated fuel assembly, the 12 MeV X-ray pulse was used in synchronization with the switch-in of the detector, and then clear cross section CT image could be successfully obtained. This technique makes it possible to observe the inner condition of irradiated fuel assembly (maximum radioactivity:2$$times$$10$$^{16}$$Bq) by non-destructive method for the first time in the world.

Oral presentation

Irradiation behavior of MA-containing MOX fuel, 2; Non-destructive PIE results of the fuel pin irradiated for short term (10minutes)

Ishimi, Akihiro; Katsuyama, Kozo; Abe, Kazuyuki; Nagamine, Tsuyoshi; Nakamura, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Development of design technology on thermal-hydraulic performance in tight-lattice rod bundles, 2; Measurement of rod-bowing effect test assembly by X-ray CT technique

Katsuyama, Kozo; Misawa, Susumu*; Mitsutake, Toru*; Misawa, Takeharu; Nagamine, Tsuyoshi; Nakamura, Yasuo; Onuki, Akira; Akimoto, Hajime

no journal, , 

no abstracts in English

Oral presentation

Irradiation behavior of MA-containing MOX fuel, 6; Non-destructive PIE results of fuel pins irradiated for short term (24 hours)

Ishimi, Akihiro; Katsuyama, Kozo; Abe, Kazuyuki; Nagamine, Tsuyoshi; Nakamura, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Irradiation behavior of MA-containing MOX fuel, 5; X-ray CT results of the fuel irradiated for short term (24 hours)

Katsuyama, Kozo; Abe, Kazuyuki; Nagamine, Tsuyoshi; Nakamura, Yasuo; Misawa, Susumu*

no journal, , 

no abstracts in English

26 (Records 1-20 displayed on this page)