Refine your search:     
Report No.
 - 
Search Results: Records 1-4 displayed on this page of 4
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Measurement of LBE flow velocity profile by UDVP

Kikuchi, Kenji; Takeda, Yasushi*; Obayashi, Hiroo*; Tezuka, Masao*; Sato, Hiroshi

Journal of Nuclear Materials, 356(1-3), p.273 - 279, 2006/09

 Times Cited Count:11 Percentile:60.11(Materials Science, Multidisciplinary)

Measurements of LBE flow velocity profile were realized in the spallation target model by the ultrasonic Doppler velocity profile technique. Hitherto, it has not yet been done well because both of poor wetting property of LBE with stainless steels and poor performance of supersonic probes at high temperatures. Measurement was made for a return flow in the target model, which has coaxially arranged annular and tube channels. The electromagnetic pump generates LBE flow and the flow rate was measured by the electromagnetic flow meter. Measurement results show that re-circulation occurred near the surface of beam window, which might affect a heat transfer of target container.

Journal Articles

Evaluation of residual tritium in stainless steel irradiated at SINQ target 3

Kikuchi, Kenji; Nakamura, Hirofumi; Tsujimoto, Kazufumi; Kobayashi, Kazuhiro; Yokoyama, Sumi; Saito, Shigeru; Yamanishi, Toshihiko

Journal of Nuclear Materials, 356(1-3), p.157 - 161, 2006/09

 Times Cited Count:5 Percentile:36.24(Materials Science, Multidisciplinary)

A high-energy proton of 580MeV at SINQ target generates almost all constituents through spallation process with hydrogen and helium gases. For the SINQ target hydrogen and helium are generated to hundreds appm H and tens appm He, respectively. However, tritium gas production has not been yet reported. Evaluation of tritium gas generation in the specimens of target 3 was done by calculation. Results were compared with gamma spectrum measurement. Residual tritium measurement was carried by the thermal desorption method. It is found that a release of tritium began over 250$$^{circ}$$C and material included 4 MBq/g. The ratio of residual tritium to generated one is estimated to be less than 20%.

Journal Articles

Development of aluminum (Al5083)-clad ternary Ag-In-Cd alloy for JSNS decoupled moderator

Teshigawara, Makoto; Harada, Masahide; Saito, Shigeru; Oikawa, Kenichi; Maekawa, Fujio; Futakawa, Masatoshi; Kikuchi, Kenji; Kato, Takashi; Ikeda, Yujiro; Naoe, Takashi*; et al.

Journal of Nuclear Materials, 356(1-3), p.300 - 307, 2006/09

 Times Cited Count:9 Percentile:53.29(Materials Science, Multidisciplinary)

We adopted silver-indium-cadmium (Ag-In-Cd) alloy as a material of decoupler for decoupled moderator in JSNS. However, from the heat removal and corrosion protection points of view, the Ag-In-Cd alloy is needed to clad between Al alloys (Al5083). We attempted to obtain good bonding conditions for between Al5083 and ternary Ag-In-Cd alloys by HIPing tests. The good HIP condition was found for small test piece ($$Phi$$20mm). Though a hardened layer due to the formation of AlAg$$_{2}$$ was found in the bonding layer, the rupture strength of the bonding layer was more than 20 MPa, which was the calculated design stress. Bonding tests of a large size piece (200$$times$$200$$times$$30 mm$$^{3}$$), which simulated the real scale, were also performed according to the results of small size tests. The result also gave good bonding and enough required-mechanical-strength, however the rupture strength of the large size test was smaller than that of small one.

Journal Articles

Microstructural evolution of SINQ irradiated austenitic stainless steels

Sawai, Tomotsugu; Kitsunai, Yuji*; Saito, Shigeru; Kikuchi, Kenji

Journal of Nuclear Materials, 356(1-3), p.118 - 121, 2006/09

 Times Cited Count:5 Percentile:36.24(Materials Science, Multidisciplinary)

A type 316 stainless steel 316F and Ti-modified type 316 stainless steel JPCA irradiated in SINQ were examined using transmission electron microscopy. Estimated irradiation temperature for two 316F specimens were 250-300$$^{circ}$$C and that for the JPCA specimen was 255$$^{circ}$$C. Irradiation damage of these specimens is calculated to be about 10 dpa. Frank loops up to 30 nm and larger perfect loops up to 50 nm were observed in 316F irradiated at 300$$^{circ}$$C. Frank loops observed in JPCA is somewhat smaller, suggesting lower dislocation bias in JPCA.

4 (Records 1-4 displayed on this page)
  • 1