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Journal Articles

Mechanical properties of pure tungsten and tantalum irradiated by protons and neutrons at the Swiss spallation-neutron source

Saito, Shigeru; Suzuki, Kazuhiro; Obata, Hiroki; Dai, Y.*

Nuclear Materials and Energy (Internet), 34, p.101338_1 - 101338_9, 2023/03

 Times Cited Count:2 Percentile:50.96(Nuclear Science & Technology)

In this study, a post-irradiation examination of pure tungsten (W) and tantalum (Ta) specimens irradiated at the Swiss Spallation-Neutron Source is conducted. W is used as a potential candidate for a solid spallation-target material owing to its favorable properties. However, W also suffers from several disadvantages such as poor corrosion resistance to water coolant and irradiation embrittlement. To improve these properties, cladding technologies using Ta for W alloys have been developed. In the present study, we investigated the irradiation effects on two tungsten materials, poly-crystal W (W-Poly) and single-crystal W (W-Sin), along with pure polycrystalline Ta. The tensile-test results revealed that W-Poly exhibited almost no ductility after irradiation of 10.2-35.0 dpa. W-Sin was irradiated up to 10.2 dpa and demonstrated 6% of total elongation (TE). With regard to Ta, TE decreased based on the increase in irradiation, reaching almost zero at doses of more than 10.3 dpa.

Journal Articles

Fabrication of a tantalum-clad tungsten target for KENS

Kawai, Masayoshi*; Kikuchi, Kenji; Kurishita, Hiroaki*; Li, J.*; Furusaka, Michihiro*

Journal of Nuclear Materials, 296(1-3), p.312 - 320, 2001/07

 Times Cited Count:47 Percentile:93.81(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Design of the solid target structure and the study on the coolant flow distribution in the solid target using the 2-dimensional flow analysis

Haga, Katsuhiro; Susuki, Akira*; Terada, Atsuhiko*; Ishikura, Shuichi*; Teshigawara, Makoto; Kinoshita, Hidetaka; Kobayashi, Kaoru*; Kaminaga, Masanori; Hino, Ryutaro

JAERI-Tech 99-081, p.43 - 0, 1999/11

JAERI-Tech-99-081.pdf:2.53MB

no abstracts in English

JAEA Reports

Heat transfer performance of a thermal entrance region of the narrow ribbed-surface channel

*; *; Kaminaga, Masanori; Hino, Ryutaro; Sudo, Yukio

JAERI-Tech 99-019, 22 Pages, 1999/02

JAERI-Tech-99-019.pdf:0.96MB

no abstracts in English

Journal Articles

Spallation target development at JAERI; R&Ds on thermo-mechanical design

Hino, Ryutaro; Kaminaga, Masanori; Aso, Tomokazu; Kogawa, Hiroyuki; Ishikura, Shuichi*; *; Terada, Atsuhiko; Kinoshita, Hidetaka; Haga, Katsuhiro

Proc. of 14th Meeting of the Int. Collaboration on Advanced Neutron Sources (ICANS-14), 1, p.252 - 268, 1998/00

no abstracts in English

JAEA Reports

Study on an accelerator driven fission reactor

; Sakuma, Minoru; Harada, Hideo

PNC TN9410 95-072, 39 Pages, 1995/04

PNC-TN9410-95-072.pdf:1.35MB

Study was performed on hybrid systems of a subcritical fission reactor driven by an accelerator last year. A system using solid core fuel and a solid target was concluded to have the highest technical feasibility among them. The system of the highest feasibility was studied this year. The system studied this year uses a subcritical LMFR based on a reactor like "JOYO" and the accelerator. The study was specially focused on a core, the accelerator and reconstracted parts of the reactor. The chief end of the reconstraction is for building a plant to grasp plant characteristics of burning TRU. The objective of a reconstracted plant is acquirement of experimental data and actual results on burning TRU by changing its core geometrical parameters. Therefore the policy of the reconstruction is conserving the present state of the reactor as far as possible. Component exchange is performed only on its upper core structure. Concerning the core, its target part consists of 19 target assemblies made of tangsten and its fuel part surrounding the target part consists of fuel assemblies made of TRU metal or oxide. Core height is 1 m. Four control rods are set in the core in order to get flat power density distribution there. A proton linear accelerator of the capability of 500Mev and 10mA is adopted as the accelerator for the hybrid system. The proton accelerator is set at the south west direction part of the reactor where there are few buildings. In addition to the above, reconstruction arrangements, items required to get a liscence and RD items are studied in this report.

Journal Articles

Development and operation of first wall in JT-60U high-power heated discharges

Masaki, Kei; ; Arai, Takashi; Hiratsuka, Hajime; Yagyu, Junichi; Saido, Masahiro; Ogiwara, Norio; Higashijima, Satoru

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), p.638 - 641, 1995/00

no abstracts in English

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