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論文

Monopole-driven shell evolution below the doubly magic nucleus $$^{132}$$Sn explored with the long-lived isomer in $$^{126}$$Pd

Watanabe, H.*; Lorusso, G.*; 西村 俊二*; Otsuka, T.*; Ogawa, K.*; Xu, Z. Y.*; 炭竃 聡之*; S$"o$derstr$"o$m, P.-A.*; Doornenbal, P.*; Li, Z.*; et al.

Physical Review Letters, 113(4), p.042502_1 - 042502_6, 2014/07

 被引用回数:24 パーセンタイル:76.91(Physics, Multidisciplinary)

A new isomer with a half-life of 23.0(8) ms has been identified in $$^{126}$$Pd at 2406 keV excitation. The proposed spin and parity configuration is 10$$^{+}$$, with maximally aligned configuration of two $$h$$$$_{11/2}$$ neutron hole. $$beta$$-decay from the long-lived isomer was also observed to populated excited states at high spins in $$^{126}$$Ag. The small energy difference between the 10$$^{+}$$ and 7$$^{-}$$ isomers in $$^{126}$$Pd was interpreted in the frame of the monopole shift of the 1$$h$$$$_{11/2}$$ neutron orbit. The effects of the monopole interaction on the evolution of single-neutron energies below $$^{132}$$Sn are discussed in terms of central and tensor forces.

口頭

Study on coating technic to enhance accident tolerance of fuel cladding, 3; Irradiation behavior of the Cr coated MDA cladding

Mohamad, A. B.; Chien, J.; 井岡 郁夫; 鈴木 恵理子; 近藤 啓悦; 根本 義之; 大久保 成彰; 山下 真一郎; 岡田 裕史*; 佐藤 大樹*

no journal, , 

As a candidate for accident tolerent fuel (ATF) cladding tubes, chromium (Cr) coated Zry cladding tubes are being developed. To realize the Cr-coated Zry cladding for future cladding application, the integrity of this material needs to be confirmed with the reactor environment conditions. In order to understand an effect of irradiation on the Cr-coated Zry cladding, ion irradiation test is carried out on the cross-sectional specimens. In this study, the following content mainly focuses on the microstructural evolution and mechanical behavior induced by ion irradiation in Cr-coated Zry cladding. The 10 MeV-Fe$$^{3+}$$ irradiation was chosen to induce the damage on the cross section of the Cr-coated Zry cladding. The sample was irradiated at 350 $$^{o}$$C and the peak irradiation damage was approximately 30 dpa. TEM-EDS shows that the Fe-enrichment peaks are observed around 15 nm at the interface regions between the coating and the Zry substrate for the sample irradiated up to 30 dpa. In addition, the hardness of irradiated sample is higher compared to that un-irradiated sample as result of irradiation-induced hardening. The details of the irradiation effect on the un- and irradiated Cr-coated Zry cladding will be discussed in detail during the presentation.

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