Magnetism of kagome metals (FeCo)Sn studied by SR

Cai, Y.*; Yoon, S.*; Sheng, Q.*; Zhao, G.*; Seewald, E. F.*; Ghosh, S.*; Ingham, J.*; Pasupathy, A. N.*; Queiroz, R.*; Lei, H.*; et al.

Physical Review B, 111(21), p.214412_1 - 214412_17, 2025/06

https://doi.org/10.1103/PhysRevB.111.214412

We study the magnetic properties of the metallic kagome system (FeCo)Sn by a combination of muon spin relaxation (SR), magnetic susceptibility, and scanning tunneling microscopy (STM) measurements in single crystal specimens with Co concentrations = 0, 0.11, 0.8. In the undoped antiferromagnetic compound FeSn, we find possible signatures for a previously unidentified phase that sets in at ~K, well beneath the Neel temperature ~K as indicated by a peak in the relaxation rate 1/ observed in zero field (ZF) and longitudinal field (LF) SR measurements, with a corresponding anomaly in the ac and dc susceptibility, and an increase in the static width 1/ in ZF-SR measurements. No signatures of spatial symmetry breaking are found in STM down to 7~K. Related to the location and motion of muons in FeSn, we confirmed a previous report that about 40% of the implanted muons reside at a field-cancelling high symmetry site at ~K, while an onset of thermal hopping changes the site occupancy at higher temperatures. In FeCoSn, where disorder eliminated the field-cancellation effect, all the implanted muons exhibit precession and/or relaxation in the ordered state. In FeCoSn, we find canonical spin glass behavior with freezing temperature ~K; the ZF and LF-SR time spectra exhibit results similar to those observed in dilute alloy spin glasses CuMn and AuFe, with a critical behavior of at and as . The absence of spin dynamics at low temperatures makes a clear contrast to the spin dynamics observed by SR in many geometrically frustrated spin systems on insulating kagome, pyrochlore, and triangular lattices. The spin glass behavior of CoSn doped with dilute Fe moments is shown to originate primarily from the randomness of doped Fe moments rather than due to geometrical frustration of the underlying lattice.

Reduction of accident occurrence frequencies by taking safety measures for defense-in-depth level 4 in a sodium-cooled fast reactor

西野 裕之; 栗坂 健一; 鳴戸 健一*; 権代 陽嗣; 山本 雅也

Mechanical Engineering Journal (Internet), 11(2), p.23-00409_1 - 23-00409_15, 2024/04

https://doi.org/10.1299/mej.23-00409

シビアアクシデントに対する安全対策の有効性評価は日本の高速実験炉「常陽」の再稼働にも必要となる。それらの安全対策には深層防護レベル4の中の対策も含まれる。既往研究では、出力運転時のレベル1PRAを実施し、深層防護レベル1から3までの安全対策の失敗の事故シーケンスの発生頻度を計算、支配的な事故シーケンスグループの同定、支配的な事故シーケンスの同定を実施した。このような成果に基づき、本研究では深層防護レベル4の対策によって発生頻度の減少を示す出力運転時のレベル1PRAを実施した。結果、各事故シーケンスグループの発生頻度は減少し、発生頻度は約1E-6/炉年となった。既往研究で算出した発生頻度と比べて本研究で算出した発生頻度は1/1000倍になった。崩壊熱除去喪失が全ての事故カテゴリの中で最も支配的であった。

Verification of probabilistic fracture mechanics analysis code PASCAL for reactor pressure vessel

Lu, K.; 高見澤 悠; Li, Y.; 眞崎 浩一*; 高越 大輝*; 永井 政貴*; 南日 卓*; 村上 健太*; 関東 康祐*; 八代醍 健志*; et al.

Mechanical Engineering Journal (Internet), 10(4), p.22-00484_1 - 22-00484_13, 2023/08

https://doi.org/10.1299/mej.22-00484

A probabilistic fracture mechanics (PFM) analysis code, PASCAL, has been developed by Japan Atomic Energy Agency for failure probability and failure frequency evaluation of reactor pressure vessels (RPVs) considering neutron irradiation embrittlement and thermal transients. To strengthen the applicability of PASCAL, considerable efforts on verifications of the PASCAL code have been made in the past years. As a part of the verification activities, a working group consisted of different organizations from industry, universities and institutes, was established in Japan. In the early phase, the working group focused on verifying the PFM analysis functions for RPVs in pressurized water reactors (PWRs) subjected to pressurized thermal shock (PTS) events. Recently, the PASCAL code has been improved in order to run PFM analyses for both RPVs in PWRs and boiling water reactors (BWRs) subjected to a broad range of transients. Simultaneously, the working group initiated a verification plan for the improved PASCAL through independent PFM analyses by different organizations. Concretely, verification analyses for a PWR-type RPV subjected to PTS transients and a BWR-type RPV subjected to a low-temperature over pressure transient were performed using PASCAL. This paper summarizes those verification activities, including the verification plan, analysis conditions and results. Based on the verification studies, the reliability of PASCAL for probabilistic integrity assessments of Japanese RPVs was confirmed with confidence.

Mechanical properties of pure tungsten and tantalum irradiated by protons and neutrons at the Swiss spallation-neutron source

斎藤 滋; 鈴木 和博; 小畑 裕希; Dai, Y.*

Nuclear Materials and Energy (Internet), 34, p.101338_1 - 101338_9, 2023/03

https://doi.org/10.1016/j.nme.2022.101338

固体ターゲットを用いる核破砕中性子源のターゲット材料及び被覆材料は、高エネルギー陽子及び核破砕中性子の照射により損傷を受ける。核破砕条件における材料の照射損傷特性を明らかにするために、スイスのPSIを中心として核破砕ターゲット材料照射プログラム(STIP: SINQ Target Irradiation Program)が進行中である。本プログラムでは、PSIの加速器で各種材料を580MeVの陽子で照射し、参加国がPIEを分担して行っている。原子力機構も照射試料の一部を輸送し、照射後試験を行った。本発表ではSTIP-II試料の中からWとTaの引張り試験の結果を報告する。これらの試料の照射条件は照射温度が130-380C、はじき出し損傷量が10.2-35.0dpaであった。引張り試験の結果、WのうちW-Polyは照射によって脆化し、伸びがほぼ0で、弾性域で破断した。W-Sinは10.2dpa照射後も全伸び約6%を示し、延性を保っていた。Taは、10.3dpa照射試料が0.7-2.6%の全伸びを示したほかは伸びがほぼ0で、弾性域で破断した。

Sodium-cooled Fast Reactors

大島 宏之; 森下 正樹*; 相澤 康介; 安藤 勝訓; 芦田 貴志; 近澤 佳隆; 堂田 哲広; 江沼 康弘; 江連 俊樹; 深野 義隆; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

https://shop.elsevier.com/books/sodium-cooled-fast-reactors/morishita/978-0-12-824076-2

ナトリウム冷却高速炉(SFR: Sodium-cooled Fast Reactor)の歴史や、利点、課題を踏まえた安全性、設計、運用、メンテナンスなどについて解説する。AIを利用した設計手法など、SFRの実用化に向けた設計や研究開発についても述べる。

Benchmark analysis by Beremin model and GTN model in CAF subcommittee

廣田 貴俊*; 名越 康人*; 北条 公伸*; 岡田 裕*; 高橋 昭如*; 勝山 仁哉; 上田 貴志*; 小川 琢矢*; 八代醍 健志*; 大畑 充*; et al.

Proceedings of ASME 2021 Pressure Vessels and Piping Conference (PVP 2021) (Internet), 9 Pages, 2021/07

In order to establish a guideline for fracture evaluation by considering plastic constraint in the ductile-brittle transition temperature (DBTT) region, the CAF (Constraint-Based Assessment of Fracture in Ductile-Brittle Transition Temperature Region) subcommittee has been launched in 2018 in the Japan Welding Engineering Society. In the committee, fracture tests are conducted using C(T), SE(B), and 50mm-thick flat plate with a surface flaw subjected to bending load or tensile load to verify fracture evaluation methods. Since simulation results are easily affected by analysis conditions, benchmark analysis is essential for the potential users of the guideline. Therefore, benchmark analyses are executed on brittle and ductile damages by Beremin and Gurson-Tvergaard-Needleman (GTN) models implemented in the finite element (FE) codes. The benchmark analyses are carried out in four steps; Step 0 is to confirm the output of FE codes in each member with the same input data and the same FE model. Step 1 is to confirm the result of Weibull stress analysis for C(T) specimens tested at -125C. The Weibull parameter, m, was fixed in this step. At step 2, sensitivity analyses are conducted on Weibull stresses in different conditions. The outputs by the GTN model are also confirmed. At the final step, the fracture simulation will be run for flat plate specimens with less plastic constraint than the standard fracture toughness specimen. As the results of the benchmark analyses up to step 2, a significant difference is not observed in the Weibull stress computed by committee members with the same input data and FE model and it is confirmed that the effects of element type, nonlinear deformation theory employed in FE analysis. For the calculation of the Weibull parameter m by using the fracture toughness test results and the developed programs by committee members, the converged values of m show good agreement among them.

Experimental validation of tensile properties measured with thick samples taken from MEGAPIE target

斎藤 滋; 鈴木 和博; 畠山 祐一; 鈴木 美穂; Dai, Y.*

Journal of Nuclear Materials, 534, p.152146_1 - 152146_16, 2020/06

https://doi.org/10.1016/j.jnucmat.2020.152146

流動鉛ビスマス共晶合金(LBE)中で照射されたMEGAPIE(MEGAwatt Pilot Experiment)ターゲットからT91引張試験片を採取し、照射後試験(PIE)を行った。これらの試験片は照射試験における標準的な試験片と比べて2倍以上の厚さがあり、そのゲージ部の厚さと幅の比(t/w)は標準的な照射用試験片とは大きく異なる。PIEの結果、これらは標準的な試験片と比較して1.5-2.0倍大きな全伸び(TE)を示し、これよりt/wとTEは強く相関していることが示唆された。そこで、未照射の試料を用いて、引張り特性に対するt/wの影響を調べた。その結果、強度と均一伸びにはt/w依存性が見られないが、TEはt/wの増加とともに大きくなることが分かった。さらに実験データに基づいて、TEを様々なt/wの試験片と相関させることで、標準試験片を含む適切なTE値を評価できることを示した。

A New approach for measuring the muon anomalous magnetic moment and electric dipole moment

阿部 充志*; Bae, S.*; Beer, G.*; Bunce, G.*; Choi, H.*; Choi, S.*; Chung, M.*; da Silva, W.*; Eidelman, S.*; Finger, M.*; et al.

Progress of Theoretical and Experimental Physics (Internet), 2019(5), p.053C02_1 - 053C02_22, 2019/05

https://doi.org/10.1093/ptep/ptz030

この論文はJ-PARCにおける、ミューオン異常磁気モーメントと電気双極子モーメント(EDM) を測定する新しいアプローチを紹介する。我々の実験のゴールは、これまでと独立の、1/10の運動量と1/20のストレージリングを用いて、とをこれまでにない精密な磁場で測定することである。さらに過去の実験との顕著な違いは、1/1000の横エミッタンスミューオンビーム(サーマルミューオンビーム)を用い、効率的なソレノイドへ縦入射し、ミューオンからの崩壊陽電子をトラッキングし、その小さな運動量ベクトルを求める点である。は統計精度450ppb、系統誤差70ppb、EDMについては ecmの精度で測定することを目標とする。

Spin excitations in optimally P-doped BaFe(AsP) superconductor

Hu, D.*; Yin, Z.*; Zhang, W.*; Ewings, R. A.*; 池内 和彦*; 中村 充孝; Roessli, B.*; Wei, Y.*; Zhao, L.*; Chen, G.*; et al.

Physical Review B, 94(9), p.094504_1 - 094504_7, 2016/09

AA2016-0252.pdf:2.18MB

https://doi.org/10.1103/PhysRevB.94.094504

最適Pドープされた超伝導体BaFe(AsP) (T=30K)におけるスピン励起の温度及びエネルギー依存性が非弾性中性子散乱実験を使って調べられた。我々の実験結果は密度汎関数理論や動的平均場理論で予想される計算結果と矛盾しておらず、BaFe(AsP)における平均プニクトゲン高さの減少が、電子相関の強さを弱め、磁気励起の有効バンド幅の増加に寄与することを示唆している。

An Experimental investigation on self-leveling behavior of debris beds using gas-injection

Cheng, S.; 山野 秀将; 鈴木 徹; 飛田 吉春; 権代 陽嗣*; 中村 裕也*; Zhang, B.*; 松元 達也*; 守田 幸路*

Experimental Thermal and Fluid Science, 48, p.110 - 121, 2013/07

https://doi.org/10.1016/j.expthermflusci.2013.02.014

Although in the past, several experiments have been conducted to investigate the self-leveling behavior of debris beds, most of these were under comparatively lower gas velocities, the findings of which might be not directly applicable to actual reactor accident conditions. Current experiments were conducted using gas-injection in a large-scale cylindrical tank, in which nitrogen gas, water and different kinds of solid particles, simulate the fission gas, coolant and fuel debris, respectively. During experiments, to accomplish the bubble-based leveling as expected in reactor conditions, two experimental approaches, termed respectively as the gas pre-charge method and the pressure-adjustment method, have been attempted. Through elaborate comparisons and evaluations, it is found that compared to the gas pre-charge way the pressure-adjustment method can alleviate the liquid disturbance from bottom inlet pipelines more effectively. Further, based on experimental data using pressure-adjustment method, influence of particle size, particle density and gas flow rate on the leveling has been confirmed under current higher gas velocities. In addition, the liquid convection in the water pool, which is not evident within lower gas velocities, is observed to play an important role within current conditions, especially for experimental runs using larger-size but lower-density particles at rather higher gas flow rates.