Zobrazeno 1 - 10
of 18
pro vyhledávání: '"Itaru Shibahara"'
Publikováno v:
Journal of Nuclear Materials. 225:267-272
Thirteen kinds of isotropic graphites with different density and maximum grain size were irradiated in the experimental fast reactor “JOYO” to fluences from 2.11 to 2.86 × 10 26 n/m 2 ( E > 0.1 MeV) at temperatures from 549 to 597°C. Postirradi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7db11bd2d3914393c3b328d77d5e4d61
https://doi.org/10.1016/0022-3115(95)00051-8
https://doi.org/10.1016/0022-3115(95)00051-8
Publikováno v:
Journal of Nuclear Materials. :487-491
Modified Type-316 and higher-nickel advanced austenitic steels were irradiated in the FFTF and JOYO fast reactors to a neutron dose as high as 210 dpa. At temperatures greater than 500°C, P-, Si-, and Ti-bearing cold-worked austenitic steels showed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7119bf131ff5e2d9f1a87ef5ad943a5b
https://doi.org/10.1016/0022-3115(94)90109-0
https://doi.org/10.1016/0022-3115(94)90109-0
Autor:
Makoto Harada, Sakae Shikakura, Takushi Ito, Shinichi Koyama, Yoshinori Sato, Shigeharu Ukai, Itaru Shibahara, Shigeo Nomura
Publikováno v:
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan. 36:441-455
Advanced austenitic stainless steel beyond the standard composition region of SUS316 stainless steel PNC1520 has been successfully developed. Optimization of the steel leads to a composition of 15Cr-20Ni-0.06C-2.5Mo-1.7Mn-0.25Ti-0.1Nb-0.028P-0.004B t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1eb4f1001a943a680f9fa6bf7e383be0
https://doi.org/10.3327/jaesj.36.441
https://doi.org/10.3327/jaesj.36.441
Publikováno v:
Journal of Nuclear Materials. 207:159-168
Type 316 stainless steel from the core of the experimental fast breeder reactor (FBR) JOYO was examined by the slow strain rate tensile (SSRT) test in pure, oxygenated-water and air and by the electrochemical potentiokinetic reactivation (EPR) test t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::902994de8d102b95ebd53cf1935cea75
https://doi.org/10.1016/0022-3115(93)90258-z
https://doi.org/10.1016/0022-3115(93)90258-z
Publikováno v:
Journal of Nuclear Materials. 204:131-140
Neutron irradiation behavior of PNC316 stainless steel, which has been developed for prototype fast breeder reactor MONJU, was investigated up to a maximum dose of 185 dpa. Excellent swelling and creep properties of PNC316 were confirmed and are beli
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::97c64690e19bdd81b8d5ea39197afa7a
https://doi.org/10.1016/0022-3115(93)90209-h
https://doi.org/10.1016/0022-3115(93)90209-h
Publikováno v:
Journal of Nuclear Materials. 204:102-108
Experimental fast reactor “Joyo” attained first criticality of its Mk-II core (irradiation core) in 1982. Peak burnup and fluence has reached 83 MWd/kg M and 10 × 1026 n/m2 (E > 0.1 MeV), respectively. Evaluation of the performance of Joyo Mk-II
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::78a3b4947095a0246eedc14418fbfc32
https://doi.org/10.1016/0022-3115(93)90205-d
https://doi.org/10.1016/0022-3115(93)90205-d
Autor:
Masanori Yamazaki, Hideo Kayano, Minoru Narui, Yoichi Kano, Itaru Shibahara, Hiroaki Kurishita
Publikováno v:
Materials Transactions, JIM. 34:1042-1052
In order to develop the small specimen technology in Charpy impact testing, the effects of V-notch dimensions on the test results were investigated for miniaturized specimens of a ferritic steel, Japanese Ferrite/Martensite Dual Phase Steel (JFMS). T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::655d8b70644b5039b7d504a54c4f1268
https://doi.org/10.2320/matertrans1989.34.1042
https://doi.org/10.2320/matertrans1989.34.1042
Publikováno v:
Journal of Nuclear Materials. :874-878
Oxide dispersion strengthened (ODS) ferritic steels were irradiated in a high voltage electron microscope (HVEM) to study their response to irradiation. Fe-13Cr with 0.25 wt% Y2O3 as dispersed particles and containing additions of either 0.45% Nb, 0.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::08f64a2defa40814a342922e607f6a3f
https://doi.org/10.1016/0022-3115(92)90598-f
https://doi.org/10.1016/0022-3115(92)90598-f
The small specimen technology is required in mechanical testing of irradiated materials because of very limited irradiation volume in currently available high flux reactors and future accelerator-based high energy neutron sources. In order to develop
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::51c139d444eb04c3630344f01c03fb12
https://doi.org/10.1520/stp16508s
https://doi.org/10.1520/stp16508s
