Muon spin relaxation in mixed perovskite (LaAlO)(SrAlTaO) with

伊藤 孝; 髭本 亘; 幸田 章宏*; 中村 惇平*; 下村 浩一郎*

Interactions (Internet), 245(1), p.25_1 - 25_7, 2024/12

https://doi.org/10.1007/s10751-024-01866-5

We report on muon spin relaxation (SR) measurements in a mixed perovskite compound, (LaAlO)(SrAlTaO) with (LSAT), which is widely used as a single-crystalline substrate for thin film deposition. In zero applied field (ZF), muon depolarization due to the distribution of nuclear dipole fields was observed in the temperature range from 4 K to 270 K. Interestingly, SR time spectra in ZF maintained a Gaussian-like feature over the entire range, while the depolarization rate exhibited a monotonic decrease with increasing temperature. This behavior may be attributed to the thermally activated diffusion of muons between a few adjacent sites within a confined space of the angstrom scale, where the motionally averaged local field that each muon experiences can remain non-zero and result in maintaining the Gaussian-like line shape. The spatial distribution of electrostatic potential at lattice interstices evaluated via density functional theory calculations suggests that such a restriction of muon diffusion paths can be caused by the random distribution of cations with different nominal valences in the mixed perovskite lattice.

Sm synchrotron-radiation-based Mssbauer and SR studies of SmRuGe

筒井 智嗣; 伊藤 孝; 中村 仁*; 吉田 実生*; 小林 義男*; 依田 芳卓*; 中村 惇平*; 幸田 章宏*; 東中 隆二*; 青木 大*; et al.

Interactions (Internet), 245(1), p.55_1 - 55_9, 2024/12

https://doi.org/10.1007/s10751-024-01900-6

Sm SR-based Mssbauer and muon spin relaxation (SR) spectroscopies have been applied to SmRuGe. The temperature dependence of the Sm SR-based Mssbauer spectra in the paramagnetic state implies the presence of dynamical nuclear Zeeman and/or quadrupole interactions. The time differential SR spectra also exhibit a marked temperature dependence in the paramagnetic state, indicating the presence of magnetic fluctuation in SmRuGe at least. These results in the present work infer that the dynamical hyperfine interactions observed using the mutually complementary spectroscopic methods are connected with the mechanism of the heavy fermion behavior in SmRuGe.

Polarized and unpolarized neutron scattering for magnetic materials at the triple-axis spectrometer PONTA in JRR-3

中島 多朗*; 齋藤 開*; 小林 尚暉*; 川崎 卓郎; 中村 龍也; 古川 はづき*; 浅井 晋一郎*; 益田 隆嗣*

Journal of the Physical Society of Japan, 93(9), p.091002_1 - 091002_5, 2024/09

https://doi.org/10.7566/JPSJ.93.091002

Neutron scattering is a powerful tool to study magnetic structures and cross-correlated phenomena originated from symmetry of the magnetic structures in matter. Among a number of neutron scattering techniques, polarized neutron scattering is quite sensitive to the orientations of the magnetic moments, which are essential to understand microscopic mechanisms of the spin-driven emergent phenomena. Here, we present POlarized Neutron Triple-Axis spectrometer PONTA in the Japan Research Reactor 3 (JRR-3), and show the present capabilities of polarized and unpolarized neutron scattering by introducing recent results from the instrument.

Effects on a bending pipe behaviour via simple pre-loading for considering functional limitations of piping in industrial facilities

杉浦 歩*; 滝藤 聖崇; 古屋 治*; 中村 いずみ*; 奥田 幸彦

Proceedings of 31st International Conference on Nuclear Engineering (ICONE31) (Internet), 8 Pages, 2024/08

The authors has been studied the effect of initial plastic deformation on the load displacement relationship of elbow of different wall thicknesses made of carbon steel. Specifically, the authors conducted load testing for elbow when three cycles of sinusoidal input with frequency of 0.02 Hz were applied to one end of the test specimen. In the load testing, for investigating effect of difference of wall thickness and initial deformation, three types of test specimens with different wall thicknesses were loaded under three different initial deformation. Next, in the finite element analysis (FEA), the same conditions are applied in the analyses that were performed for three types of piping with different wall thicknesses before and after plastic deformation. The effect of initial displacement on the load - displacement relationship was confirmed by loading test, and analytical investigations were also considered. Thus, in this paper, the authors show the two mainly obtained results as organizations of the some issues to improve the accuracy of the analysis with large deformation. Firstly, from the comparison of the test and analytical results confirmed that the load - displacement relationship, the results could be shown as an initial plastic deformation caused not only decreasing in primary stiffness but also decreasing maximum load, on all load testing cases. And then, relative errors in the maximum loads between load testing and FEA results were observed that the errors on maximum loads of tension were larger than those of compression. Secondly, focusing on the wall thickness, the trends of relative errors of the maximum load could be shown when the wall thickness increase the errors on maximum loads of compression. However the trends of the errors on maximum loads of tension were shown completely different.

Benchmark analysis on pipe support structures for establishing inelastic seismic design

中村 いずみ*; 滝藤 聖崇; 嶋津 龍弥*; 奥田 幸彦; 酒井 理哉*; 大谷 章仁*; 渡壁 智祥; 奥田 貴大; 渋谷 忠弘*; 白鳥 正樹*

Proceedings of ASME 2024 Pressure Vessels & Piping Conference (PVP 2024) (Internet), 9 Pages, 2024/07

A new seismic design procedure which evaluates the inelastic behavior of piping system by detailed finite element method (FEM) analysis has been developed in Japan (the JSME CC); however, the inelastic behavior is only considered for pipe body in the JSME CC, and the evaluation of inelastic behavior of pipe support structure is still not included. To clarify the current analytical accuracy of inelastic analysis of pipe support structures and to develop an analytical guideline to reasonably include the inelastic behavior of pipe support structure in the seismic design of piping system, a series of benchmark analysis on pipe support structures has been launched in 2022. The benchmark analysis of pipe support structures consists of mainly two stages; the first stage is the analysis of pipe support structures themselves, and the second stage is the analysis of piping system with inelastic support structure. As of January 2024, the first stage of benchmark analysis is in progress. It is confirmed that there are some variabilities in modeling of support structures, stress-strain relationship, and boundary conditions. The load-deflection relationships also show variability even when the support structures are in the elastic region. The effect of these variations to the response of piping system model is remained as future tasks.

プルトニウム転換技術開発施設における放射性物質含有スラッジの安定化処理

谷川 聖史; 中村 大司; 浅川 直也*; 瀬谷 和仁*; 大森 二美男*; 小磯 勝也*; 堀籠 和志; 清水 靖之

JAEA-Technology 2024-001, 37 Pages, 2024/05

JAEA-Technology-2024-001.pdf:2.32MB

プルトニウム転換技術開発施設の廃液処理工程で発生した中和沈殿焙焼体及び凝集沈殿焙焼体(スラッジ)については、ポリ容器に収納し梱包用のビニルバッグで密封して、各々中和沈殿焙焼体はグローブボックスに、凝集沈殿焙焼体は施設内の保管場所に保管している。これらスラッジは、保管中においてスラッジ中に含有する水分等が放射性元素由来の線等により放射線分解されて発生するガスにより、梱包するビニルバッグの膨らみが確認されていた。このため、1983年の操業開始以降、スラッジを梱包したビニルバッグの膨らみを定期的に確認し、膨らみを確認したものはビニルバッグの交換を行うことで、安全に保管管理を実施してきた。スラッジからの放射線分解によるガスの発生を防止し、保管時の安全性を向上させるために、ガスの発生原因となっているスラッジ中の吸湿性のある硝酸ナトリウム塩を取り除く安定化処理作業を2018年8月から開始し、2022年8月まで実施した。その安定化処理としてスラッジの水洗浄処理を実施した結果、スラッジ中に含まれるナトリウム濃度を3wt%以下まで低減することができた。また、そのスラッジは1年以上にわたって各々の保管場所で保管していた際に、保管に使用している梱包用のビニルバッグに膨らみがなく、かつガスの発生原因となるスラッジの含水率に増加は認められないことを確認したことから、保管中の安全性が向上していること及び今後、放射線分解によるガスの発生はないものと評価した。安定性が確認できた中和沈殿焙焼体は、粉末缶に収納し粉末貯蔵エリアに保管廃棄した。これにより、中和沈殿焙焼体及び凝集沈殿焙焼体において、内部からのガスの発生によるリスクがなくなり、保管時の安全性を向上することができた。

Recent status of the cryogenic sample environment at the MLF, J-PARC

石角 元志*; 高橋 竜太*; 山内 康弘*; 中村 雅俊*; 石丸 宙*; 山内 沙羅*; 河村 聖子; 吉良 弘*; 坂口 佳史*; 渡辺 真朗; et al.

JPS Conference Proceedings (Internet), 41, p.011010_1 - 011010_7, 2024/05

https://doi.org/10.7566/JPSCP.41.011010

Recent status of cryogenic sample environment equipment at the Materials and Life Science Experimental Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC) has been reported. We have reviewed the specifications and performance of cryogenic sample environment equipment and a newly installed Gifford-McMahon (GM) cryofurnace, which are mainly managed by the Cryogenic and Magnet group in the sample environment team at the MLF. Moreover, the recent maintenance and update of each piece of equipment, the improved temperature-control function, and the expansion of the usable beamline of the cryogenic sample environment equipment are described.

A Systematic approach for the adequacy analysis of a set of experimental databases; Application in the framework of the ATRIUM activity

Baccou, J.*; Glantz, T.*; Ghione, A.*; Sargentini, L.*; Fillion, P.*; Damblin, G.*; Sueur, R.*; Iooss, B.*; Fang, J.*; Liu, J.*; et al.

Nuclear Engineering and Design, 421, p.113035_1 - 113035_16, 2024/05

https://doi.org/10.1016/j.nucengdes.2024.113035

In the Best-Estimate Plus Uncertainty (BEPU) framework, the use of best-estimate code requires to go through a Verification, Validation and Uncertainty Quantification process (VVUQ). The relevance of the experimental data in relation to the physical phenomena of interest in the VVUQ process is crucial. Adequacy analysis of selected experimental databases addresses this problem. The outcomes of the analysis can be used to select a subset of relevant experimental data, to encourage designing new experiments or to drop some experiments from a database because of their substantial lack of adequacy. The development of a specific transparent and reproducible approach to analyze the relevance of experimental data for VVUQ still remains open and is the topic of this contribution. In this paper, the concept of adequacy initially introduced in the OECD/NEA SAPIUM (Systematic APproach for model Input Uncertainty quantification Methodology) activity is formalized. It is defined through two key properties, called representativeness and completeness, that allows considering the multifactorial dimension of the adequacy problem. A new systematic approach is then proposed to analyze the adequacy of a set of experimental databases. It relies on the introduction of two sets of criteria to characterize representativeness and completeness and on the use of multi-criteria decision analysis method to perform the analysis. Finally, the approach is applied in the framework of the new OECD/NEA ATRIUM activity which includes a set of practical IUQ exercises in thermal-hydraulics to test the SAPIUM guideline in determining input uncertainties and forward propagating them on an application case. It allows evaluating the adequacy of eight experimental databases coming from the Super Moby-dick, Sozzi-Sutherland and Marviken experiments and identifying the most adequate ones.

Measurements of the neutron total and capture cross sections and derivation of the resonance parameters of Ta

遠藤 駿典; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之; Rovira Leveroni, G.; 藤 暢輔; 瀬川 麻里子; 前田 亮

Nuclear Science and Engineering, 198(4), p.786 - 803, 2024/04

https://doi.org/10.1080/00295639.2023.2227826

The neutron transmission ratio and capture yield for Ta were measured in J-PARC MLF ANNRI to improve the accuracy of resonance parameters. The total cross section was determined from the transmission ratio in the energy range from 0.2 to 150 eV. The capture cross section was obtained from the capture yield using the pulse height weighting technique (PHWT) in the energy range from thermal to 150 eV. The obtained transmission ratio and capture cross-section were fitted by the resonance analysis code, REFIT, and the resonance parameters were determined below 150 eV. It was also discussed the correlations caused by fitting based on statistical uncertainty and correlations for systematic uncertainty based on sample thickness in the transmission measurements.

Damage status definition of piping system in industrial plants for mitigation of natech risk due to closure on elbows

滝藤 聖崇; 奥田 幸彦; 中村 いずみ*; 古屋 治*

Transactions of the 27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27) (Internet), 10 Pages, 2024/03

産業事故の類型のうち、設計想定を超える巨大地震などの外的事象を起因とする産業事故を特にNATECH(Natural-hazard triggered technological accidents)と呼ばれている。火災や化学物質の大規模漏洩につながった事例が過去複数あったことから、現在ではNATECHが周辺住民、周辺環境に大きく影響を及ぼすものとして注目されている。このため、プラントのリスク評価とそれに基づいたプラントのNATECH対策は不可欠である。しかしながら、プラントのリスク評価に必要な、プラントを構成する機器の損傷モードとシステムの機能維持との関係を定量的にあらわす「損傷状態」の定義は未だ確立されていない。そこで、本研究では、原子力施設をはじめとしたプラントを構成する代表的なシステムである配管システムを例にとり、損傷モードにおける「損傷状態」の定義に資する指標を提案することを目的とする。配管の主要な損傷モードのひとつである流路閉塞のモードがプラントの機能維持に影響を及ぼすと考えられるため、まずは流路閉塞に着目し、配管のうち特に変形しやすい要素であるエルボを対象に、試験および解析の両面から閉塞率と変形量の関係を求めた。本論文では、上記試験結果等を報告するとともに、得られた閉塞率を流路閉塞の損傷モードにおける、機能維持に関わる「損傷状態」の定義に資する指標のひとつとして提案する。