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Revising the 4${it f}$ symmetry in CeCu$$_{2}$$Ge$$_{2}$$; Soft X-ray absorption and hard X-ray photoemission spectroscopy

荒谷 秀和*; 中谷 泰博*; 藤原 秀紀*; 川田 萌樹*; 金井 惟奈*; 山神 光平*; 藤岡 修平*; 濱本 諭*; 久我 健太郎*; 木須 孝幸*; et al.

Physical Review B, 98(12), p.121113_1 - 121113_6, 2018/09

 被引用回数:1 パーセンタイル:59.26(Materials Science, Multidisciplinary)

We present a detailed study on the $$4f$$ ground state symmetry of the pressure-induced superconductor CeCu$$_2$$Ge$$_2$$ probed by soft X-ray absorption and hard X-ray photoemission spectroscopy. The revised Ce $$4f$$ ground states are determined as $$|{Gamma_7}rangle=sqrt{0.45}|{J_{z}=pm frac{5}{2}}rangle - sqrt{0.55}|{mp frac{3}{2}}rangle$$ with $$Sigmamathchar`-{rm type}$$ in-plane rotational symmetry. This gives an in-plane magnetic moment consistent with the antiferromagnetic moment as reported in neutron measurements. Since the in-plane symmetry is the same as that for the superconductor CeCu$$_2$$Si$$_2$$, we propose that the charge distribution along the $$c$$-axis plays an essential role in driving the system into a superconducting phase.


Development of crack evaluation models for probabilistic fracture mechanics analyses of Japanese reactor pressure vessels

Lu, K.; 眞崎 浩一; 勝山 仁哉; Li, Y.

Proceedings of 2018 ASME Pressure Vessels and Piping Conference (PVP 2018), 8 Pages, 2018/07

In Japan, a probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed by Japan Atomic Energy Agency for structural integrity assessment of reactor pressure vessels (RPVs). The most recent release is PASCAL Version 4 (hereafter, PSACAL4) which can be used to evaluate the failure frequency of RPVs considering neutron irradiation embrittlement and pressurized thermal shock events. For the integrity assessment of RPVs, development of crack evaluation models is important. In this study, finite element analyses are performed firstly to verify the stress intensity factor calculations of cracks in PASCAL4. In addition, the applicability of the crack evaluation models in PASCAL4 such as the location of embedded cracks, crack shape and depth of surface cracks, and the increment of crack propagation is investigated. Based on sensitivity analyses of crack evaluation models for Japanese RPVs using PASCAL4, the effects of these evaluation models on failure frequency are clarified. From the analysis results, crack evaluation models recommended to the failure frequency evaluation for a Japanese model RPV are discussed.


Development of probabilistic fracture mechanics analysis code PASCAL Version 4 for reactor pressure vessels

Lu, K.; 眞崎 浩一; 勝山 仁哉; Li, Y.; 宇野 隼平*

Proceedings of 2018 ASME Pressure Vessels and Piping Conference (PVP 2018), 10 Pages, 2018/07

In Japan, Japan Atomic Energy Agency has developed a PFM analysis code PASCAL (PFM Analysis of Structural Components in Aging LWRs) for structural integrity assessment of Japanese reactor pressure vessels (RPVs) considering neutron irradiation embrittlement and pressurized thermal shock transients. By reflecting the latest knowledge and findings, the PASCAL code has been continuously improved. In this paper, the development of PASCAL Version 4 (hereafter, PASCAL4) is described. Several analysis functions incorporated into PASCAL4 for evaluating the failure frequency of RPVs are introduced, for example, the evaluation function of confidence level of failure frequency considering epistemic and aleatory uncertainties in probabilistic variables, the recent stress intensity factor (KI) solutions and KI calculation methods considering complicated stress distributions, and the recent Japanese irradiation embrittlement prediction method. Finally, using PASCAL4, a PFM analysis example for a Japanese model RPV is presented.


Verification of probabilistic fracture mechanics analysis code through benchmark analyses

Li, Y.; 宇野 隼平*; 眞崎 浩一; 勝山 仁哉; Dickson, T.*; Kirk, M.*

Proceedings of 2018 ASME Pressure Vessels and Piping Conference (PVP 2018), 11 Pages, 2018/07

A probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed in Japan Atomic Energy Agency to evaluate failure probabilities and failure frequencies of Japanese reactor pressure vessels (RPVs) considering pressurized thermal shock (PTS) events and neutron irradiation embrittlement, based on Japanese methods and data. To verify PASCAL, we have been carrying out benchmark analyses with a PFM code FAVOR which has been developed in the United States and utilized in nuclear regulation. Through two year activities, the applicability of PASCAL in failure probability and failure frequency evaluation of Japanese RPVs was confirmed with great confidence. The analysis conditions and results are provided in this paper.



勝山 仁哉; 眞崎 浩一; 宮本 裕平*; Li, Y.

JAEA-Data/Code 2017-015, 229 Pages, 2018/03




Verification methodology and results of probabilistic fracture mechanics code PASCAL

眞崎 浩一; 宮本 裕平*; 小坂部 和也*; 宇野 隼平*; 勝山 仁哉; Li, Y.

Proceedings of 2017 ASME Pressure Vessels and Piping Conference (PVP 2017) (CD-ROM), 7 Pages, 2017/07



Verification of probabilistic fracture mechanics analysis code PASCAL

Li, Y.; 勝又 源七郎*; 眞崎 浩一*; 林 翔太郎*; 板橋 遊*; 永井 政貴*; 鈴木 雅秀*; 関東 康祐*

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 10 Pages, 2017/07



PASCAL信頼性向上ワーキンググループ活動報告; 平成27年度

Li, Y.; 林 翔太郎*; 板橋 遊*; 永井 政貴*; 関東 康祐*; 鈴木 雅秀*; 眞崎 浩一*

JAEA-Review 2017-005, 80 Pages, 2017/03




Three-dimensional electronic structures and the metal-insulator transition in Ruddlesden-Popper iridates

山崎 篤志*; 藤原 秀紀*; 橘 祥一*; 岩崎 大昌*; 東野 勇志*; 吉見 千秋*; 中川 広野*; 中谷 泰博*; 山神 光平*; 荒谷 秀和*; et al.

Physical Review B, 94(11), p.115103_1 - 115103_10, 2016/11


 被引用回数:11 パーセンタイル:24.6(Materials Science, Multidisciplinary)

軟X線角度分解光電子分光を用いて、Ruddlesden-Popper型イリジウム酸化物Sr$$_{n+1}$$Ir$$_{n}$$O$$_{3n+1}$$の3次元バンド構造を調べた。その結果、IrO$$_{2}$$面構造の次元性の増加と共に発現する金属-絶縁体転移に関する直接的な証拠を得た。この転移は、スピンー軌道結合により生じた$$j_{eff}$$ = 1/2バンドがフェルミエネルギーを横切ることにより生じる。入射光エネルギーを350eV以上走査することにより、SrIrO$$_{3}$$の3次元フェルミ面形状及び、Sr$$_{3}$$Ir$$_{2}$$O$$_{7}$$$$k_{z}$$依存した光電子強度の振動を明らかにした。本手法は、電子状態の全体像の理解において非常に有効である。


Benchmark analyses of probabilistic fracture mechanics for cast stainless steel pipe

北条 公伸*; 林 翔太郎*; 西 亘*; 釜谷 昌幸*; 勝山 仁哉; 眞崎 浩一*; 永井 政貴*; 岡本 年樹*; 高田 泰和*; 吉村 忍*

Mechanical Engineering Journal (Internet), 3(4), p.16-00083_1 - 16-00083_16, 2016/08



Study on application of PFM analysis method to Japanese code for RPV integrity assessment under PTS events

小坂部 和也*; 眞崎 浩一*; 勝山 仁哉; 勝又 源七郎; 鬼沢 邦雄; 吉村 忍*

Proceedings of 2015 ASME Pressure Vessels and Piping Conference (PVP 2015) (Internet), 8 Pages, 2015/07



Estimation of through-wall cracking frequency of RPV under PTS events using PFM analysis method for identifying conservatism included in current Japanese code

小坂部 和也*; 眞崎 浩一*; 勝山 仁哉; 勝又 源七郎; 鬼沢 邦雄

Proceedings of 2014 ASME Pressure Vessels and Piping Conference (PVP 2014) (DVD-ROM), 7 Pages, 2014/07



Probabilistic structural integrity analysis of reactor pressure vessels during pressurized thermal shock events

眞崎 浩一; 勝山 仁哉; 鬼沢 邦雄

Journal of Pressure Vessel Technology, 136(1), p.011208_1 - 011208_7, 2014/02

 パーセンタイル:100(Engineering, Mechanical)




鈴木 貞明; 柳生 純一; 正木 圭; 西山 友和; 中村 誠俊; 佐伯 寿; 星 亮; 澤井 弘明; 長谷川 浩一; 新井 貴; et al.

NIFS-MEMO-67, p.266 - 271, 2014/02



Effect of partial welding on the residual stress and structural integrity of piping welds

勝山 仁哉; 眞崎 浩一; 鬼沢 邦雄

Journal of Pressure Vessel Technology, 135(6), p.061403_1 - 061403_8, 2013/12

 パーセンタイル:100(Engineering, Mechanical)



Assembly study for JT-60SA tokamak

柴沼 清; 新井 貴; 長谷川 浩一; 星 亮; 神谷 宏治; 川島 寿人; 久保 博孝; 正木 圭; 佐伯 寿; 櫻井 真治; et al.

Fusion Engineering and Design, 88(6-8), p.705 - 710, 2013/10

 被引用回数:8 パーセンタイル:29.95(Nuclear Science & Technology)

The JT-60SA project is conducted under the BA satellite tokamak programme by EU and Japan, and the Japanese national programme. The project mission is to contribute to early realization of fusion energy by supporting ITER and by complementing ITER with resolving key physics and engineering issues for DEMO reactors. In this paper, the assembly of major tokamak components such as VV and TFC is mainly described. An assembly frame (with the dedicated cranes), which is located around the tokamak, is adopted to carry out the assembly of major tokamak components in the torus hall independently of the facility cranes for preparations such as pre-assembly in the assembly hall. The assembly frame also provides assembly tools and jigs to support temporarily the components as well as to adjust the components in final positions.



西川 弘之*; 眞崎 浩一*; 勝山 仁哉; 鬼沢 邦雄

日本原子力学会和文論文誌, 12(3), p.211 - 221, 2013/09



Study on the structural integrity of RPV using PFM analysis concerning inhomogeneity of the heat-affected zone

眞崎 浩一; 勝山 仁哉; 鬼沢 邦雄

E-Journal of Advanced Maintenance (Internet), 5(2), p.85 - 92, 2013/08




政木 清孝*; 亀島 洋平*; 久森 紀之*; 佐野 雄二*; 秋田 貢一; 菖蒲 敬久

材料, 62(5), p.297 - 304, 2013/05



高経年化技術評価の高度化; 原子炉圧力容器の健全性評価

鬼沢 邦雄; 眞崎 浩一; 小坂部 和也*; 西川 弘之*; 勝山 仁哉; 西山 裕孝

日本保全学会第9回学術講演会要旨集, p.374 - 379, 2012/07


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