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Electrochemical behavior of carbon steel with bentonite/sand in saline environment

北山 彩水; 谷口 直樹; 三ツ井 誠一郎

Materials and Corrosion, 72(1-2), p.211 - 217, 2021/01

 被引用回数:0 パーセンタイル:0(Materials Science, Multidisciplinary)

Current designs for the geological disposal of high-level radioactive wastes in Japan use carbon steel overpack containers surrounded by a mixed bentonite/sand buffer material, which will be located in a purpose built repository deep in the underground. There are suitable sites for a repository in Japan, however coastal areas are preferred from a logistics point of view. It is therefore important to perform the long-term performance of the carbon steel overpack and mixed bentonite/sand buffer material in the saline groundwaters of coastal areas. In the current study, the passivation behavior and initial corrosion rates of carbon steel with and without mixed bentonite/sand were tested as a function of pH in representative saline groundwaters. The main findings of the current study indicate that passivation of carbon steel with buffer material will be difficult in a saline environment, even at high pH = 12 conditions, and that the corrosion rate of carbon steel was more strongly affected by the presence of buffer material than by the concentration.



梅田 良太; 下山 一仁; 栗原 成計

日本原子力学会和文論文誌, 19(4), p.234 - 244, 2020/12



Proposal of laser-induced ultrasonic guided wave for corrosion detection of reinforced concrete structures in Fukushima Daiichi Nuclear Power Plant decommissioning site

古澤 彰憲; 竹仲 佑介; 西村 昭彦

Applied Sciences (Internet), 9(17), p.3544_1 - 3544_12, 2019/09

 被引用回数:6 パーセンタイル:72.92(Chemistry, Multidisciplinary)



Preliminary verification of water radiolysis and ECP calculation models by in-pile ECP measurements

塙 悟史; 端 邦樹; 知見 康弘; 笠原 茂樹

Proceedings of 21st International Conference on Water Chemistry in Nuclear Reactor Systems (Internet), 12 Pages, 2019/09

Water radiolysis and ECP calculations models were preliminary verified using in-pile ECP and related measurement data obtained under BWR and PWR simulated conditions. Two separate anodic polarization curves were supposed in ECP calculations in order to deal with the material surface condition changed by water chemistry, and the measured ECP under BWR simulated conditions were well explained by the calculations. ECP calculations under PWR simulated conditions were also carried out supposing the other polarization curve applicable to the temperature range of 593 K and good agreement between the measurement and the calculations was obtained.


Effect of re-oxidation rate of additive cations on corrosion rate of stainless steel in boiling nitric acid solution

入澤 恵理子; 山本 正弘; 加藤 千明; 本岡 隆文; 伴 康俊

Journal of Nuclear Science and Technology, 56(4), p.337 - 344, 2019/04

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

The boiling nitric acid solution containing highly oxidizing cations dissolved from the spent nuclear fuels corrodes stainless steels because of the nobler corrosion potential and their fast reduction rate. The cations themselves are re-oxidized to higher oxidizing states in a bulk solution after the corrosion reaction. In this paper, the re-oxidation rate constants of typical cations, such as Cr, V, Pu, and Np, were analyzed, and discussed about the effect on time dependencies of the corrosion rate. It was indicated that the cations with a large re-oxidation rate constant, such as Np, could keep the corrosion rate at high level continuously for the long immersion duration.


各種環境での電気化学測定; 原子力II(地層処分)深部地下環境における炭素鋼の腐食モニタリング

谷口 直樹; 中山 雅

材料と環境, 67(12), p.487 - 494, 2018/12



Corrosion behaviour of FeCrAl-ODS steels in nitric acid solutions with several temperatures

高畠 容子; 安倍 弘; 佐野 雄一; 竹内 正行; 小泉 健治; 坂本 寛*; 山下 真一郎

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 9 Pages, 2018/10

事故耐性軽水炉燃料の燃料被覆管として開発されているFeCrAl-ODS鋼の硝酸腐食評価を、使用済燃料再処理工程に対して燃料被覆管腐食生成物が与える影響を評価するために実施した。3mol/L硝酸における腐食試験を、60$$^{circ}$$C, 80$$^{circ}$$C,沸騰条件において実施し、浸漬試験の試験片に対してはXPS分析を行った。沸騰条件にて最も腐食が進展し、腐食速度は0.22mm/yであった。酸化被膜内のFe割合は減少しており、CrとAlの割合は増加していた。腐食試験の結果、FeCrAl-ODS鋼は高い硝酸腐食耐性を持つため、再処理工程中の溶解工程において許容可能であることを確かめた。


Mass transfer inside narrow crevice of SUS316L in high temperature water

山本 正弘; 相馬 康孝; 五十嵐 誉廣; 上野 文義

Proceedings of Annual Congress of the European Federation of corrosion (EUROCORR 2018) (USB Flash Drive), 7 Pages, 2018/09



Effects of environmental factors inside the crevice on corrosion of stainless steel in high temperature water

山本 正弘; 佐藤 智徳; 五十嵐 誉廣; 上野 文義; 相馬 康孝

Proceedings of European Corrosion Congress 2017 (EUROCORR 2017) and 20th ICC & Process Safety Congress 2017 (USB Flash Drive), 6 Pages, 2018/09



幌延深地層研究計画におけるオーバーパック腐食試験; 模擬オーバーパック、緩衝材およびヒーターの製作、設置

中山 雅

JAEA-Technology 2018-006, 43 Pages, 2018/08




Flow-accelerated corrosion of type 316L stainless steel caused by turbulent lead-bismuth eutectic flow

Wan, T.; 斎藤 滋

Metals, 8(8), p.627_1 - 627_22, 2018/08

 被引用回数:5 パーセンタイル:43.06(Materials Science, Multidisciplinary)

In this study, an LBE loop referred to as JLBL-1 was used to experimentally study the behavior of 316L SS when subjected to FAC for 3000 h under non-isothermal conditions. An orifice tube specimen, consisting of a straight tube that abruptly narrows and widens at each end, was installed in the loop. The specimen temperature was 450 centigrade, and a temperature difference between the hottest and coldest legs of the loop was 100 centigrade. The oxygen concentration in the LBE was less than 10$$^{-8}$$ wt.%. The Reynolds number in the test specimen was approximately 5.3$$times$$10$$^{4}$$. The effects of various hydrodynamic parameters on FAC behavior were studied with the assistance of computational fluid dynamics (CFD) analyses, and then a mass transfer study was performed by integrating a corrosion model into the CFD analyses. The results show that the local turbulence level affects the mass concentration distribution in the near-wall region and therefore the mass transfer coefficient across the solid/liquid interface. The corrosion depth was predicted on the basis of the mass transfer coefficient obtained in the numerical simulation and was compared with that obtained in the loop; the two results agreed well.


An Empirical model for the corrosion of stainless steel in BWR primary coolant

内田 俊介*; 塙 悟史; 内藤 正則*; 岡田 英俊*; Lister, D. H.*

Corrosion Engineering, Science and Technology, 52(8), p.587 - 595, 2017/10

 被引用回数:2 パーセンタイル:17.39(Materials Science, Multidisciplinary)



Effect of chloride ion on corrosion behavior of SUS316L-grade stainless steel in nitric acid solutions containing seawater components under $$gamma$$-ray irradiation

佐野 雄一; 安倍 弘; 竹内 正行; 飯嶋 静香; 内田 直樹

Journal of Nuclear Materials, 493, p.200 - 206, 2017/09

 被引用回数:5 パーセンタイル:58.67(Materials Science, Multidisciplinary)



Improving the corrosion resistance of silicon carbide for fuel in BWR environments by using a metal coating

石橋 良*; 田邊 重忠*; 近藤 貴夫*; 山下 真一郎; 永瀬 文久

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09



Performance degradation of candidate accident-tolerant cladding under corrosive environment

永瀬 文久; 坂本 寛*; 山下 真一郎

Corrosion Reviews, 35(3), p.129 - 140, 2017/08

 被引用回数:8 パーセンタイル:51.83(Electrochemistry)



Status of LBE corrosion test loop "OLLOCHI" and experiments at JAEA

斎藤 滋; 大久保 成彰; 大林 寛生; 佐々 敏信

NEA/CSNI/R(2017)2 (Internet), p.195 - 200, 2017/06

原子力機構において研究が進められている加速器駆動システム(ADS: Accelerator Driven System)では、核破砕ターゲット及び炉心冷却材として鉛ビスマス共晶合金(LBE; Lead-Bismuth Eutectic)が採用される。将来のADSやJ-PARCに建設が計画されている、ADSターゲット実験施設(TEF-T)の実現には、LBEに関する多くの解決すべき課題がある。特に、T91(改良9Cr-1Mo鋼)やSUS316Lなどの鋼材に関して、400-550$$^{circ}$$Cの温度範囲で酸素濃度制御下かつLBE流動下の腐食データは不可欠である。原子力機構では高温での腐食データを得るために、"OLLOCHI (Oxygen-controlled LBE LOop Corrosion tests in HIgh-temperature)"と名付けられた新しい腐食試験ループを設計・製作した。高温部配管はT91製で、加熱器や膨張タンク容器は2.25Cr-1Mo鋼製である。これら高温部の最高温度は550$$^{circ}$$Cである。低温部は配管、機器類ともにSUS316L製で、これら低温部の最高温度は450$$^{circ}$$Cである。2016年春までにOLLOCHIは、加熱器や試験片交換ボックスなどの改造と、LBE無しでの調整運転を終えた。酸素センサーと酸素濃度制御システムは間もなく導入され、その後LBE有りでの調整運転と酸素濃度制御試験を開始する予定である。さらに来春までに分岐した試験部それぞれにも流量計が付加される予定である。これらの試験や改造と平行して、試験片ホルダー内の流れの分布を明らかにするため、試験部の流動解析を行う予定である。


Development of metal corrosion testing method simulating equipment of reprocessing of spent nuclear fuels

松枝 誠; 入澤 恵理子; 加藤 千明; 松井 寛樹

Proceedings of 54th Annual Meeting of Hot Laboratories and Remote Handling (HOTLAB 2017) (Internet), 4 Pages, 2017/00



In situ X-ray diffraction study of the oxide formed on alloy 600 in borated and lithiated high-temperature water

渡邉 真史*; 米澤 利夫*; 菖蒲 敬久; 城 鮎美; 庄子 哲雄*

Corrosion, 72(9), p.1155 - 1169, 2016/09

 被引用回数:0 パーセンタイル:0.01(Materials Science, Multidisciplinary)

In situ X-ray diffraction (XRD) measurements of the oxide film formed on Alloy 600 in borated and lithiated high-temperature water were conducted to demonstrate a capability to investigate rapid changes in oxide films during transient water chemistry conditions. In the presence of dissolved hydrogen (DH) = 30 cm$$^{3}$$/kg [H$$_{2}$$O] and dissolved oxygen (DO) $$<$$ 0.06 ppm, only spinel oxides were detected and no significant NiO peak was found even after 1,220 h exposure. By contrast, once the DO was increased to 8 ppm, a NiO peak grew rapidly. Within 7 h, the amount of NiO became comparable to that of spinel oxide. However, when DO was decreased again below 0.3 ppm and DH was increased up to 30 cm$$^{3}$$/kg [H$$_{2}$$O], the ratio of NiO to spinel did not change during 10 h. Thus, the rate of dissolution of NiO in DH = 30 cm$$^{3}$$/kg water seemed to be lower than the growth rate of NiO in high DO conditions.


The Effect of crystal textures on the anodic oxidization of zirconium in a boiling nitric acid solution

加藤 千明; 石島 暖大; 上野 文義; 山本 正弘

Journal of Nuclear Science and Technology, 53(9), p.1371 - 1379, 2016/09


 被引用回数:2 パーセンタイル:25.63(Nuclear Science & Technology)

硝酸水溶液でジルコニウムの応力腐食割れに関して、ジルコニウムの陽極酸化に及ぼす結晶配向の影響を調査した。酸化ジルコニウム膜の成長挙動は、脱不動態化電位(1.47V vs. SSE)で、劇的に変化した。1.5Vでは、酸化皮膜は速く成長し、その平均皮膜厚さは電荷量に比例して増加した。酸化皮膜は周期的な3乗則に従った成長挙動を示した。周期的な3乗則に従った成長挙動への遷移前では、酸化皮膜の成長挙動に結晶配向の影響を及ぼさなかった。しかし、皮膜成長の遷移後は、酸化皮膜の平均皮膜厚さと厚い酸化皮膜の下に生じたき裂は結晶配向の影響を受けた。(0002)面が配向している圧延面では、その平均皮膜厚さは減少し、皮膜内のき裂により皮膜の剥離が生じた。(0002)面に垂直面である圧延方向面では、厚い酸化皮膜の下には、圧延方向に深く進展したき裂が観察された。き裂は酸化物層の中をジルコニウム母材の(0002)面に沿って進展した。酸化物層は、ひも状の酸化ジルコニウムとジルコニウム水素化物からなり、ひも状の酸化ジルコニウムは、単斜晶ZrO$$_{2}$$に加えて斜方晶ZrO$$_{2}$$を含んでいた。外部応力が無い条件でき裂が発生・進展した機構の1つの仮定として、(0002)面に析出した水素化物の酸化と、その後に生じる斜方晶ZrO$$_{2}$$から単斜晶ZrO$$_{2}$$への相変態がその原因の一つと考えられた。


Seawater effects on the soundness of spent fuel cladding tube

本岡 隆文; 上野 文義; 山本 正弘

Proceedings of 2016 EFCOG Nuclear & Facility Safety Workshop (Internet), 6 Pages, 2016/09


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