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Tsai, T.-H.; 佐々木 新治; 前田 宏治
Journal of Nuclear Science and Technology, 60(6), p.715 - 723, 2023/06
被引用回数：1 パーセンタイル：40.11(Nuclear Science & Technology)A method for processing and visualizing X-ray computed tomography (CT) images of a fuel assembly is developed and applied to a JOYO MK-III fuel assembly. The method provides vertical-section-like images to observe the spatial distribution of CT values in fuel pins and also supplies images that show the relationship between the linear heat rate (LHR) and radial CT-value distribution. In addition, an attempt to analyze the radial cracks in the CT images is proposed, and the results demonstrate the correlation between LHR and the radial cracks.
Grazzi, F.*; Cialdai, C.*; Manetti, M.*; Massi, M.*; Morigi, M. P.*; Bettuzzi, M.*; Brancaccio, R.*; Albertin, F.*; 篠原 武尚; 甲斐 哲也; et al.
Rendiconti Lincei. Scienze Fisiche e Naturali, 32(3), p.463 - 477, 2021/09
被引用回数：2 パーセンタイル：16.91(Multidisciplinary Sciences)In this paper, we have studied an additively manufactured metallic component, intended for ultra-high vacuum application, the exit-snout of the MACHINA transportable proton accelerator beam-line. Metal additive manufacturing components can exhibit heterogeneous and anisotropic microstructures. Two non-destructive imaging techniques, X-ray computed tomography and Neutron Tomography, were employed to examine its microstructure. They unveiled the presence of porosity and channels, the size and composition of grains and intergranular precipitates, and the general behavior of the spatial distribution of the solidification lines. While X-ray computed tomography evidenced qualitative details about the surface roughness and internal defects, neutron tomography showed excellent ability in imaging the spatial density distribution within the component. The anisotropy of the density was attributed to the material building orientation during the 3D printing process. Density variations suggest the possibility of defect pathways, which could affect high vacuum performances. In addition, these results highlight the importance of considering building orientation in the design for additive manufacturing for UHV applications.
高橋 宏明*; 舘 幸男
Applied Clay Science, 168, p.211 - 222, 2019/02
被引用回数：9 パーセンタイル：50.21(Chemistry, Physical)異なる膨潤特性をもつNa型及びCs型モンモリロナイトの微細構造と物質移行特性が、ナノフォーカスX線CTによる3次元微細構造分析と重水の拡散実験とを組み合わせて調査された。X線CT観察により、乾燥状態の圧縮Na型モンモリロナイトが飽和膨潤する過程で、連結性マクロ間隙はゲル相によって埋められ、粘土粒子のサイズは小さくなることが確認された。Cs型モンモリロナイトでは、それとは対照的に飽和過程でのゲル相の生成や粒子・間隙サイズの変化は認められなかった。X線CTによって評価された飽和Cs型モンモリロナイトの連結性マクロ間隙の屈曲度及び収れん度を含む幾何学因子は、重水の拡散試験から評価された値と整合した。Na型モンモリロナイトの場合、X線CTと拡散試験から導出された幾何学因子の差異が確認され、これは静電的相互作用による収れん度とX線CTの解像度では観察できないゲル相や層間間隙の屈曲度に起因するものと考えられた。
阿部 雄太; 山下 拓哉; 佐藤 一憲; 中桐 俊男; 石見 明洋; 永江 勇二
Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 9 Pages, 2018/07
Authors are developing an experimental technology to realize experiments simulating Severe Accident (SA) conditions using simulant fuel material (ZrO
with slight addition of MgO for stabilization) that would contribute not only to Fukushima Daiichi (1F) decommissioning but also to enhance the safety of worldwide existing and future nuclear power plants through clarification of the accident progression behavior. Based on the results of the prototype test, improvement of plasma heating technology was conducted. The Core Material Melting and Relocation (CMMR)-1/-2 experiments were carried out in 2017 with the large-scale simulated fuel assembly (1 m 
0.3 m 
) applying the improved technology (higher heating power and controlled oxygen concentration). In these two tests, heating history was different resulting basically in similar physical responses with more pronounced material melting and relocation in the CMMR-2 experiment. The CMMR-2 experiment is selected here from the viewpoint of establishing an experimental technology. The CMMR-2 experiment adopted 30-min heating period, the power was increased up to a level so that a large temperature gradient (
2,000 K/m) expected at the lower part of the core in the actual 1F accident conditions. Most of the control blade and the channel box migrated from the original position. After the heating, the simulated fuel assembly was measured by the X-ray Computed Tomography (CT) technology and by Electron Probe Micro Analyzer (EPMA). CT pictures and elemental mapping demonstrated its excellent performance with rather good precision. Based on these results, an excellent perspective in terms of applicability of the non-transfer type plasma heating technology to the SA experimental study was obtained.
阿部 雄太; 佐藤 一憲; 中桐 俊男; 石見 明洋; 永江 勇二
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 7 Pages, 2017/04
Authors are developing an experimental technology to realize experiments simulating severe accident conditions that would contribute not only to Fukushima Daiichi (1F) decommissioning but also to enhance safety of worldwide existing and future nuclear power plants through clarification of the accident progression behavior. In the first part of this program, called Phase I hereafter, a series of small-scale experiments (10 cm 10 cm 25 cmh) were performed in March 2015 and it was demonstrated that non-transfer (NTR) type plasma heating is capable of successfully melting the high melting-point ceramics. In order to confirm applicability of this heating technology to larger scale test specimens to address the experimental needs, authors performed a second series plasma heating tests in 2016, called Phase II hereafter, using a simulated fuel assembly with a larger size (100 cm 30 cm phi). In the phase II part of the program, the power was increased up to a level so that a large temperature gradient (2,000 K/m - 4,000 K/m) expected at the lower part of the core in the actual 1F accident conditions. After the heating, these test pieces were measured by the X-ray Computed Tomography (CT) technology. CT pictures demonstrated its excellent performance with rather good precision. Based on these results, basic applicability of the NTR plasma heating for the SA experimental study was confirmed. With the Phase II-type 100 cm-high test geometry, core material relocation (CMR) behavior within the active core region and its access to the core support structure region would be addressed. JAEA is also preparing for the next step large-scale tests using up to four simulated fuel assemblies covering the lower part of the active fuel and fully simulating the upper part of the lower core support structures addressing CMR behavior including core material relocation into the lower plenum.
後藤 俊治*; 竹下 邦和*; 鈴木 芳生*; 大橋 治彦*; 浅野 芳裕; 木村 洋昭*; 松下 智裕*; 八木 直人*; 一色 康之*; 山崎 裕史*; et al.
Nuclear Instruments and Methods in Physics Research A, 467-468(Part1), p.682 - 685, 2001/07
イメージング技術開発や、X線光学素子開発,物性研究のためのトモグラフィーや医学イメージング,トポグラフィー研究等を目的とした、最初の中央ビームラインをSPring-8で構築した。この結果、大視野でコヒーレントな光ビームを得ることに成功した。またこのビームラインを用いて、300mmのシリコンクリスタルのone-shotトポグラフのような、予備実験を成功裡に終わることができた。これらについて論じた。
井岡 郁夫; 依田 真一
Journal of Nuclear Materials, 151, p.202 - 208, 1988/00
被引用回数：2 パーセンタイル：31.44(Materials Science, Multidisciplinary)高温ガス試験炉に使用される黒鉛材料は、冷却材ヘリウム中に含まれる微量の不純物により酸化される。酸化により黒鉛材料の機械的性質が劣化することは、既に知られている。また、酸化モード(均一、不均一酸化)によっても、その劣化の程度は異なる。とくに、不均一酸化された黒鉛内の密度分布を非破壊的に把握することは、強度劣化を知るために重要である。そこで、最近開発されたX線CTスキャナを用いて酸化黒鉛内部の密度分布を調べた。また、同試片を外表面から切削して測定した密度分布と比較し、良い一致を得た。さらに、各種人工欠陥を導入した原子炉級黒鉛の欠陥検出も行った。
井岡 郁夫; 依田 真一; 藤井 正司*; 奥 達雄; 田中 利幸
日本原子力学会誌, 28(6), p.534 - 542, 1986/00
被引用回数：0 パーセンタイル：0.02(Nuclear Science & Technology)最近産業用として材料試験を目的としたX線CTスキャナが開発された。X線CT法は、通常の放射線法に比べ1桁以上検出感度が増すので微細な欠陥でも見付けられる利点がある。X線CTスキャナを用いて、人工欠陥を有する黒鉛材料の断面像を撮影した。その結果、IG-11の場合、円柱状欠陥で直径0.2mm、線状欠陥で幅0.1mmのものまで確認できた。また、黒鉛内部の巨視的、微視的き裂及び酸化により生じた空孔も確認できた。しかし、正確な欠陥寸法は得られなかった。更に、CT値のプロフィールより、酸化に伴う試料内部の連続的な密度変化も確認できた。X線CT法は、従来の超音波法、放射線法に比べ、より有効な非破壊検査法である。
