Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Keizo Ogata"'
Autor:
Keizo Ogata, Akihiro Yamauchi
Publikováno v:
Journal of Nuclear Science and Technology. 57:301-311
In this paper, to clarify the conditions for the occurrence of macroscopic hydrogen-induced ductile-to-brittle transitions (DBT) at operational temperatures, the effect of hydride precipitation on ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::36331a7485e4ba66c216a04b36fc2a4e
https://doi.org/10.1080/00223131.2019.1676835
https://doi.org/10.1080/00223131.2019.1676835
Autor:
Nobuo Nakae, Hitoshi Matsuoka, Toshiyasu Miyashita, Kazuo Kakiuchi, Katsuichiro Kamimura, Keizo Ogata, Toshikazu Baba
Publikováno v:
Transactions of the Atomic Energy Society of Japan. 7:380-395
The high-burnup BWR 9×9 lead use fuel assemblies (LUAs), which are designed for a maximum assembly burnup of 55 GWd/t in Japan, have been examined after irradiation in a commercial BWR to confirm the reliability of the current safety evaluation meth
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dbb90277885bba7f72d4145822f24b88
https://doi.org/10.3327/taesj.j08.004
https://doi.org/10.3327/taesj.j08.004
Publikováno v:
Journal of Nuclear Science and Technology. 43:1128-1135
Among a series of power ramp tests on 25 Zr-lined segment rods of burnup ranging from 43 to 61 GWd/t, five segment rods failed during the power ramp tests. One segment rod irradiated for 3 cycles (43 GWd/t) failed with a pinhole due to PCI/SCC. The r
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ce22b4ba7bc85fe2fb0d29762767437d
https://doi.org/10.1080/18811248.2006.9711204
https://doi.org/10.1080/18811248.2006.9711204
Publikováno v:
Journal of Nuclear Science and Technology. 41:731-740
Precipitation morphology and habit planes of the delta-phase Zr hydrides, which were precipitated within the a-phase matrix grains and along the grain boundaries of recrystallized Zircaloy-2 cladding tube, have been examined by electron backscatter d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bf85655607d5bfe5a3bdf6405bd0387f
https://doi.org/10.1080/18811248.2004.9715540
https://doi.org/10.1080/18811248.2004.9715540
Publikováno v:
Advances in Energy Materials
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b11856cebc53b24ac963152b12d0d79
https://doi.org/10.1002/9780470528976.ch6
https://doi.org/10.1002/9780470528976.ch6
Autor:
Katsuhiro Abe, Mishima Yoshitsugu, Takuya Hattori, Tadatsune Okubo, Masahisa Inagaki, Kazuo Murota, Tatsuro Kodama, Keizo Ogata, Toshimasa Aoki, Toru Fujibayashi
Out-of-reactor corrosion tests in 10.3-MPa steam at temperatures between 490 and 530°C have been carried out on Zircaloy-2 tube specimens of various fabrication histories including archive specimens of the same tube lots as were used in the commerci
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0b70a0895c31fdeeeec990b8181e2b0f
https://doi.org/10.1520/stp18871s
https://doi.org/10.1520/stp18871s
Autor:
Keizo Ogata
The cause of material variety in the nodular corrosion susceptibility was investigated through measurements of the distributions of alloying element concentrations. A Zircaloy-2 specimen surface area of 5 by 5 mm was divided into a 500 by 500 square
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2c5badd82253ee481b8abbf0461ba5a3
https://doi.org/10.1520/stp18874s
https://doi.org/10.1520/stp18874s
Autor:
Masaaki Otsu, Keizo Ogata
Publikováno v:
The Proceedings of the Materials and processing conference. :443-444
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::682e173ca321ddf9ae290a950905cb1b
https://doi.org/10.1299/jsmemp.2004.12.443
https://doi.org/10.1299/jsmemp.2004.12.443
Autor:
Toshio Kubo, Hiroaki Muta, Shinsuke Yamanaka, Masayoshi Uno, Keizo Ogata, P. Barberis, S. W. Dean
Publikováno v:
Journal of ASTM International. 8:102960
The objective of the present research is to build a modeling method for delayed hydride cracking (DHC) of zirconium alloys. DHC tests were carried out on Zircaloy-2 cladding tubes in the chamber of a scanning electron microscope to directly observe t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2f4b778aaa7ce0953d5b675dd40a796
https://doi.org/10.1520/jai102960
https://doi.org/10.1520/jai102960