Zobrazeno 1 - 10
of 14
pro vyhledávání: '"Yoshihiro Sekio"'
Autor:
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 9
A new subassembly type passive reactor shutdown device is proposed to expand the diversity and robustness of core disruptive accident prevention measures for sodium-cooled fast reactors (SFRs). The device contains pins with a fuel material that is in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9f9eae224b04a56a85ee9d8a6eb4ed7a
https://doi.org/10.1115/1.4056854
https://doi.org/10.1115/1.4056854
Autor:
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 9
Following the Fukushima Nuclear Power Plant accident in 2011, it has become increasingly important for reactor safety designs to consider measures that can prevent the occurrence of severe accidents. This report proposes a novel subassembly-type pass
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ce0cf473cd9122edb8bae8511dacfb09
https://doi.org/10.1115/1.4056834
https://doi.org/10.1115/1.4056834
Autor:
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Publikováno v:
Volume 4: SMRs, Advanced Reactors, and Fusion.
A new subassembly-type passive reactor shutdown device is proposed to expand the diversity and robustness of core disruptive accident prevention measures for sodium-cooled fast reactors (SFRs). The device contains pins with a fuel material that is in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f30ea607ef8973917c5a3cf492c3bc11
https://doi.org/10.1115/icone29-91812
https://doi.org/10.1115/icone29-91812
Autor:
Hiroshi Sagara, Isamu Sato, Koji Morita, Tatsumi Arima, Haruaki Matsuura, Masatoshi Kawashima, Koharu Kawase, Yuji Arita, Wei Liu, Yoshihiro Sekio
Publikováno v:
Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation.
After the Fukushima NPP accident in 2011, it has become increasingly important for reactor safety design to consider design measures to prevent the occurrence of severe accidents. In this study, a new subassembly-type passive reactor shutdown device
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::86f617d1371aebc2071751c272868ec6
https://doi.org/10.1115/icone28-64099
https://doi.org/10.1115/icone28-64099
Autor:
Yoshihiro Sekio, Norihito Sakaguchi
Publikováno v:
MATERIALS TRANSACTIONS. 60:678-687
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1f37b816304d6c93d90166e56a2737a1
https://doi.org/10.2320/matertrans.mc201811
https://doi.org/10.2320/matertrans.mc201811
Autor:
Yoshihiro Sekio, Yasuhide Yano, Takeji Kaito, Tomoyuki Uwaba, T. Inoue, Shigeharu Ukai, Hiroshi Oka, Tomohiro Furukawa, Satoshi Ohtsuka, Shoichi Kato, Takashi Tanno
Publikováno v:
Journal of Nuclear Materials. 516:347-353
9Cr-ODS steel claddings consisting of tempered martensitic matrix, showed prominent creep rupture strength at 1000 °C, which surpassed that of heat-resistant austenitic steels although creep rupture strength of tempered martensitic steels is general
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::111d39b99e29672a0ee0e6b9d4debbae
https://doi.org/10.1016/j.jnucmat.2019.01.052
https://doi.org/10.1016/j.jnucmat.2019.01.052
Autor:
Satoshi Ohtsuka, Yoshihiro Sekio, Hiroshi Oka, Tomoyuki Uwaba, Yasuhide Yano, Takashi Tanno, Takeji Kaito
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 324-330 (2016)
The relationship among tensile strength, Vickers hardness and dislocation density for two types of 11Cr-ferritic/martensitic steel (PNC-FMS) was investigated after aging at temperatures between 400 and 800$^{\circ}$C up to 45,000 h and after neutron
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3dadc95b998acfaa7599132e1a5d1cf3
Publikováno v:
Nuclear Materials and Energy, Vol 24, Iss, Pp 100760-(2020)
An on-line instrumented material irradiation rig (MARICO-II) was used for investigating temperature history effect for void swelling behavior in V-Fe binary alloys irradiated at a fast rector, Joyo. Neutron irradiation were performed at 477C with 7.5
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bf2bc7e920b558d6ded28c1153a4ce15
https://doi.org/10.1016/j.nme.2020.100760
https://doi.org/10.1016/j.nme.2020.100760
Publikováno v:
Metallurgical and Materials Transactions A. 46:5789-5800
Dissimilar joints between ferritic and austenitic steels are of interest for selected applications in next generation fast reactors. In this study, dissimilar friction-stir welding of an 11 pct Cr ferritic/martensitic steel to a 316 austenitic stainl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::63567697f0e378f4e774f2bd0498935c
https://doi.org/10.1007/s11661-015-3152-5
https://doi.org/10.1007/s11661-015-3152-5
Publikováno v:
Journal of Nuclear Materials. 458:355-360
Irradiation-induced void denuded zone (VDZ) formation near grain boundaries was studied to clarify the effects of minor alloying elements on vacancy diffusivity during irradiation in practical PNC316 stainless steel developed for nuclear reactor core
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::15670e92fa92ca8555657930cd9ba8af
https://doi.org/10.1016/j.jnucmat.2014.12.054
https://doi.org/10.1016/j.jnucmat.2014.12.054