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Journal Articles

Mechanical properties of austenitic stainless steels irradiated at SINQ target 4

Saito, Shigeru; Hamaguchi, Dai; Usami, Koji; Endo, Shinya; Ono, Katsuto; Matsui, Hiroki; Kikuchi, Kenji*; Kawai, Masayoshi*; Yong, D.*

Proceedings of 1st International Workshop on Technology and Components of Accelerator-driven Systems (TCADS-1) (Internet), 9 Pages, 2010/03

The research and development for an accelerator-driven system (ADS) to transmute minor actinide (MA) have been progressed. The target beam window of ADS submerged in the reactor will be subjected to high-energy proton and spallation neutron irradiation. To evaluate mechanical properties of irradiated materials, post irradiation examination (PIE) of the STIP (SINQ target irradiation program) specimens was carried out at JAEA. In the present study, PIE on austenitic steels JPCA and Alloy800H irradiated at SINQ target 4 (STIP-II) was conducted. Austenitic steels are preferable as the material for the target beam window of ADS from the view point of DBTT shift, which should be taken into consideration for ferritic / martensitic steels. The irradiation conditions were as follows: proton energy was 580 MeV, irradiation temperatures were ranged from 100 to 450$$^{circ}$$C, and displacement damage levels were ranged from 6.5 to 19.5 dpa. Tensile tests were performed in air at R.T. to 350$$^{circ}$$C. Results of the tensile tests performed at R.T. indicate that irradiation hardening occurred with increasing displacement damage level up to 10 dpa. At higher doses, irradiation hardening seemed to tend to saturate. Degradation of ductility was bottomed around 10 dpa and specimens kept its ductility until 19.5 dpa. All the specimens fractured in ductile manner.

Oral presentation

Progress in development of intense materials against radiation and beam impact, 7; Measurement of residual hydrogen and helium gases in the steels irradiated in SINQ

Kikuchi, Kenji; Hamaguchi, Dai; Saito, Shigeru; Endo, Shinya; Yong, D.*

no journal, , 

Residual hydrogen and helium gases in the materials irradiated in SINQ were measured by two different methods. The results showed that the amount of residual helium gas was within a factor two. For the case of TEM specimens the residual helium gas was scattered within a couple of tens percent in comparison with published data. Residual hydrogen could not be quantified because of measuring accuracy.

Oral presentation

MEGAPIE PIE plan

Kikuchi, Kenji; Yong, D.*; Al Mazouzi, A.*; Jean, H.*; Maloy, S.*; Lindau, R.*; Park, J. Y.*; Gr$"o$schel, F.*

no journal, , 

MEGAPIE (Megawatt Pilot Experiment) was successfully done in 2006. Components performance during high-energy proton beam bombardment under the liquid lead-bismuth flow will be studied to define ADS quality condition. Samples are cut from the spent target and distributed to collaborated organizations. PIE (Post Irradiation Experiment) will provide knowledge on materials quality evaluated by design, construction and operation. It is scheduled to pre-test in 2008-2009 and to do PIE in 2010 and 2011. Before conducting PIE round robin test is to be done in order to secure experiment technology level.

Oral presentation

Proton irradiation effects on tennsile and bend-fatigue properties of welded F82H specimens

Saito, Shigeru; Kikuchi, Kenji; Hamaguchi, Dai; Usami, Koji; Ishikawa, Akiyoshi; Nishino, Yasuharu; Endo, Shinya; Kawai, Masayoshi*; Yong, D.*

no journal, , 

In several institutes, research and development for an accelerator-driven transmutation system have been progressed. Ferritic/martensitic steels are the candidate material for the beam window. To obtain the irradiation data, the PIE work of the SINQ target irradiation program (STIP) specimens was carried out at JAEA. In this study, the results of PIE on F82H and its welded joint will be reported. The tensile tests were performed for F82H EB and TIG welded specimens. The results indicate that all specimens kept its ductility after 10 dpa irradiation and fractured in ductile manner. The fatigue life of F82H base metal is almost the same as that of unirradiated specimens. Though the number of specimen is limited, the fatigue life of F82H EB (15mm and 3.3mm) welded joints seems to increase after irradiation. The fracture surfaces of the specimens showed transgranular morphology. While F82H TIG welded specimens were not fractured by 10$$^{7}$$ cycles.

Oral presentation

Microstructural evolution on Ti-modified austenitic stainless steel irradiated by high energy proton

Hamaguchi, Dai; Kikuchi, Kenji; Saito, Shigeru; Endo, Shinya; Yong, D.*

no journal, , 

The microstructural evolutions on austenitic stainless steel JPCA irradiated in SINQ target was investigated. JPCA is Ti-modified type-316 base austenitic stainless steel for reduced swelling, and is one of the candidate materials for the structural material on Japanese ADS. Specimens were irradiated in STIP-I and STIP-II with 580MeV proton. For the sample irradiated to 5.7dpa at 150$$^{circ}$$C on STIP-I, only high density of small loops and black dot defects were observed. The density of the loops did not increase significantly with doses and temperatures, which was around 7$$times$$10$$^{22}$$m$$^{-3}$$, but the size increased from around 15nm at 5.7dpa to 25nm at 19.5dpa on STIP-II irradiated sample. On the other hand, formation of high density small He bubbles with a size of about 2 to 3nm and a density around 1 to 4$$times$$10$$^{23}$$m$$^{-3}$$ were observed for the samples irradiated more than 7.9dpa at above 200$$^{circ}$$C. The densities of the bubbles did not significantly change with doses but the sizes slightly decreased. The helium concentration for the sample with the dose of 7.9dpa was about 600appm, and for the highest dose sample with 19.5dpa was about 1600appm. The formation of bubbles on JPCA was observed at lower temperature compared to EC316LN on STIP-I irradiated samples. This might due to the Ti modification, since Ti in steel is known to be an over-size element and prefer to combine with vacancies, which leads to shorten the incubation period for cavity formation.

Oral presentation

Performance test of bend fatigue testing machine for small specimens

Endo, Shinya; Kikuchi, Kenji; Saito, Shigeru; Hamaguchi, Dai; Yong, D.*

no journal, , 

Post Irradiation Examination (PIE) of materials irradiated at SINQ, with 580 MeV proton beam, of PSI in Switzerland, has been performed under an international cooperation, which covers tensile, bending fatigue and TEM observation. There are a number of irradiated materials stored at hot laboratory and PIE has not conducted yet at PSI. We set up testing machine, developed at JAEA, to the hot laboratory of PSI in order to obtain materials design data base useful for a construction of nuclear transmutation facility. Testing machine performance was investigated by using un-irradiated specimens. Optical and SEM observation of fractured specimen was done and failure mechanism was investigated. PIE is to be done at PSI.

Oral presentation

Tensile properties of JPCA specimens irradiated in a spallation environment

Saito, Shigeru; Kikuchi, Kenji; Hamaguchi, Dai; Usami, Koji; Endo, Shinya; Ono, Katsuto; Matsui, Hiroki; Kawai, Masayoshi*; Yong, D.*

no journal, , 

no abstracts in English

Oral presentation

Bend-fatigue properties of JPCA specimens irradiated in a spallation environment

Saito, Shigeru; Hamaguchi, Dai; Endo, Shinya; Sakuraba, Naotoshi; Miyai, Hiromitsu; Kikuchi, Kenji*; Kawai, Masayoshi*; Yong, D.*

no journal, , 

no abstracts in English

Oral presentation

Mechanical properties of JPCA and Alloy800H irradiated up to 19 dpa at SINQ target4

Saito, Shigeru; Hamaguchi, Dai; Kikuchi, Kenji*; Usami, Koji; Endo, Shinya; Ono, Katsuto; Matsui, Hiroki; Kawai, Masayoshi*; Yong, D.*

no journal, , 

In several institutes, the research and development for an accelerator-driven transmutation system (ADS) to transmute minor actinide (MA) have been progressed. To evaluate lifetime of the beam window, post irradiation examination (PIE) of the STIP (SINQ target irradiation program, SINQ; Swiss spallation neutron source) specimens was carried out at JAEA. The specimens were austenitic steels JPCA and Alloy800H. The irradiation conditions of the specimens irradiated at SINQ target 4 (STIP-II) were as follows: proton energy was 580 MeV, irradiation temperatures were ranged from 100 to 450$$^{circ}$$C, and dpa were ranged from 6.5 to 19.5 dpa. All PIE works has been carried out at WASTEF and RFEF in Tokai Research and Development Center, JAEA. Tensile tests were performed in air at R.T., 250$$^{circ}$$C and 350$$^{circ}$$C. Fracture surface observation after the tests was done by SEM. Results of the tensile tests performed at R.T. indicate that irradiation hardening occurred with increasing displacement damage level up to 10 dpa. At higher doses, irradiation hardening seemed to tend to saturate. Degradation of ductility was bottomed around 10 dpa and specimens kept its ductility until 19.5 dpa. The most of specimens fractured in ductile manner, however, the specimens irradiated at the higher dose ($$>$$ 19 dpa) and higher temperature ($$>$$ 400$$^{circ}$$C) showed partially intergranular morphology.

Oral presentation

Mechanical properties of W alloys and pure Ta irradiated at SINQ target 4

Saito, Shigeru; Kikuchi, Kenji*; Hamaguchi, Dai; Suzuki, Kazuhiro; Endo, Shinya; Obata, Hiroki; Kurishita, Hiroaki*; Watanabe, Ryuzo*; Kawai, Masayoshi*; Yong, D.*

no journal, , 

no abstracts in English

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