Transactions of the Atomic Energy Society of Japan最新文献_第8页

Seismic Response Analysis of Unit 1 of Fukushima-Daiichi Nuclear Power Plant During the 2011 Off the Pacific Coast of Tohoku Earthquake Using Three-Dimensional Finite Element Method (2nd Report: Results of Eigenanalysis and Seismic Response Analysis) 基于三维有限元法的2011年日本东北地震中福岛第一核电站1号机组地震反应分析(第二次报告:本征分析与地震反应分析结果)

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/TAESJ.J18.025

S. Yoshimura, T. Miyamura, Tomonori Yamada, H. Akiba, H. Kiyoura

{"title":"Seismic Response Analysis of Unit 1 of Fukushima-Daiichi Nuclear Power Plant During the 2011 Off the Pacific Coast of Tohoku Earthquake Using Three-Dimensional Finite Element Method (2nd Report: Results of Eigenanalysis and Seismic Response Analysis)","authors":"S. Yoshimura, T. Miyamura, Tomonori Yamada, H. Akiba, H. Kiyoura","doi":"10.3327/TAESJ.J18.025","DOIUrl":"https://doi.org/10.3327/TAESJ.J18.025","url":null,"abstract":"This paper presents Part II of the report of our research on three-dimensional ﬁnite element seismic response analyses of a full-scale integrated model of the boiling water reactor and reactor building of Unit 1 at Fukushima-Daiichi Nuclear Power Plant subjected to the 2011 off the Paciﬁc coast of Tohoku Earthquake of 9.0 Mw occurring on March 11, 2011. The previous paper （ Part I ） reported the developed analysis method, i.e., the parallel structural analysis solver ADVENTURE_Solid Ver.2 and its pre- / post-modules towards the K computer, model construction, the veriﬁcation of the analysis model, and computation performance. Part II （ this paper ） reports the results of the eigenanalysis and seismic response analysis of the developed three-dimensional ﬁnite element model. These results were precisely compared with those of a lumped mass model. The overall responses of the two different models agreed reasonably well, although the three-dimensional ﬁnite element model succeeded in showing local responses more precisely. Finally, we concluded some key roles of petascale simulation for such practical and socially important problems.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"8 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437376","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 2

SCC and Crevice Corrosion Resistances of Stainless Steel Modified with Tantalum Addition 添加钽改性不锈钢的SCC和缝隙耐蚀性

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/taesj.j18.036

J. Kaneda, Yun Wang, Yusaku Maruno, M. Iwanami, S. Ishioka, N. Shigenaka, A. Hasegawa

{"title":"SCC and Crevice Corrosion Resistances of Stainless Steel Modified with Tantalum Addition","authors":"J. Kaneda, Yun Wang, Yusaku Maruno, M. Iwanami, S. Ishioka, N. Shigenaka, A. Hasegawa","doi":"10.3327/taesj.j18.036","DOIUrl":"https://doi.org/10.3327/taesj.j18.036","url":null,"abstract":"In this paper, several modiﬁed stainless steels （ SSs ） with different contents of Ta （ 0.13 – 0.61 ％） and C （ 0.010 – 0.046 ％） were produced to measure the electrochemical potentiokinetic reactivation （ EPR ） ratio and investigate their crevice corrosion resistance, stress corrosion cracking （ SCC ） susceptibility and crack growth rate （ CGR ） in a simulated boiling water reactor （ BWR ） environment. As a result of the EPR tests, we found that the Ta / C ratio must be ≥ 13 to suppress sensitization by sta-bilization heat treatment. If the Ta / C ratio is ≥ 19, sensitization can be suppressed without stabiliza-tion heat treatment. In the crevice corrosion test under γ -ray irradiation, the maximum corrosion depth in the Ta-modiﬁed SSs was smaller than that in type 316L SS. Ta-modiﬁed SSs had better crevice corrosion resistance than 316L SS. In the creviced bent beam test, there was no SCC in any of the Ta-modiﬁed SSs, whereas cracks were found in four of seven specimens of 316L SS. The CGR test was conducted using 0.5 T-compact tension specimens. Crack growth rates of the Ta-modiﬁed SSs were lower than that of 316L SS. The crevice corrosion resistance and SCC resistance were improved by Ta addition. We assumed that Ta addition can improve the repassivation response.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.3327/taesj.j18.036","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437430","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Improvement of the Simplified Hybrid Method for Seismic Risk Assessment of Nuclear Fuel Facilities 核燃料设施地震风险评估的简化混合方法改进

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/taesj.j18.037

K. Mori

引用次数: 0

High-Temperature Stability of SiO2 Oxide Film on Surface of SiC SiC表面SiO2氧化膜的高温稳定性

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/taesj.j18.044

S. Yamaguchi, A. Yusufu, Takuma Shirahama, Y. Murakami, T. Onitsuka, Masayoshi Uno

{"title":"High-Temperature Stability of SiO2 Oxide Film on Surface of SiC","authors":"S. Yamaguchi, A. Yusufu, Takuma Shirahama, Y. Murakami, T. Onitsuka, Masayoshi Uno","doi":"10.3327/taesj.j18.044","DOIUrl":"https://doi.org/10.3327/taesj.j18.044","url":null,"abstract":"SiC, which is a promising accident-tolerant fuel cladding, is a non-oxide, and it is known that pas-sive oxidation occurs, where by a protective oxide ﬁ lm of SiO 2 is formed under atmospheric conditions above 900 ℃ . The reaction occurring at this high temperature is important in assessing the soundness of SiC during a severe accident, but the understanding of it is still insuf ﬁ cient. In this study, to evalu-ate the high-temperature oxidation behavior when SiC cladding is exposed to the atmosphere （ 10 5 Pa ） during an accident involving a light-water reactor, an oxidation test was performed for up to 100 h at 1100 to 1500 ℃ . As a result, a SiO 2 oxide ﬁ lm was formed on the surface of SiC, but the formation of bubbles originating from impurities and cracks due to a phase transformation was con ﬁ rmed. In addi-tion, it was observed, for the ﬁ rst time in this research, that a multilayered SiO 2 oxide ﬁ lm was formed at 1500 ℃ . Therefore, it was shown that the oxidation reaction of SiC does not stop depending on the surrounding conditions under high temperature and atmospheric conditions.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437460","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Study on Risk Management during Decommissioning of Accident-Damaged Nuclear Power Plant 事故损坏核电站退役风险管理研究

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/TAESJ.J18.021

T. Aoki

引用次数: 2

Development of Fabrication and Inspection Technologies for Oxidation-Resistant Fuel Element for High-Temperature Gas-Cooled Reactors 高温气冷堆抗氧化燃料元件制造与检测技术的发展

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/taesj.j19.002

J. Aihara, A. Yasuda, S. Ueta, H. Ogawa, Masaki Honda, Koichiro Ohira, Y. Tachibana

引用次数: 0

Tools to Visualize and Share Relations between R&D Themes of National Project on Fukushima Daiichi Waste Management 可视化和共享福岛第一核电站废物管理国家项目研发主题之间关系的工具

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/TAESJ.J18.028

Yohei Sato, Tomoya Iwashima, Motohashi Tetsuo, M. Obata

引用次数: 0

Analysis of Chemical Behavior of Nitrogen Oxide Formed by Thermal Decomposition of FP Nitrates in Accident of Evaporation to Dryness by Boiling of Reprocessed High-Level Liquid Waste 再处理高放废液沸腾蒸发干燥事故中FP硝酸盐热分解生成氮氧化物的化学行为分析

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/TAESJ.J18.019

Kazuo Yoshida, H. Tamaki, N. Yoshida, Ryoichiro Yoshida, Y. Amano, H. Abe

{"title":"Analysis of Chemical Behavior of Nitrogen Oxide Formed by Thermal Decomposition of FP Nitrates in Accident of Evaporation to Dryness by Boiling of Reprocessed High-Level Liquid Waste","authors":"Kazuo Yoshida, H. Tamaki, N. Yoshida, Ryoichiro Yoshida, Y. Amano, H. Abe","doi":"10.3327/TAESJ.J18.019","DOIUrl":"https://doi.org/10.3327/TAESJ.J18.019","url":null,"abstract":"An accident of evaporation to dryness by boiling of high-level liquid waste （ HLLW ） is postulated as one of the severe accidents caused by the loss of cooling function at a fuel reprocessing plant. In this case, volatile radioactive materials, such as ruthenium （ Ru ） , are released from the tanks with mixed vapor of water and nitric-acid into the atmosphere. In addition, nitrogen oxides are also released, formed by the thermal decomposition of metal nitrates of ﬁssion products （ FP ） in HLLW. It has been observed experimentally that nitrogen oxide strongly affects the transport behavior of Ru under the anticipated atmospheric conditions in cells and / or compartments of the facility building. Chemical reactions of nitrogen oxide with water and nitric acid are also recognized as complex phe-nomena that undergo simultaneously in the vapor and liquid phases. An analysis method has been developed by coupling two types of computer codes to simulate not only thermohydraulic behavior but also chemical reactions in the ﬂow paths of carrier gases for quantitative estimation of the amount of Ru released to the environment. A simulation study has also been carried out with a typical facility building to demonstrate the feasibility of the developed simulation method.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.3327/TAESJ.J18.019","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437277","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Corrigendum: Demonstration of Rapid Detection System for Radioactive Cesium in the Air toward Releasing the Evacuation Order in the Difficult-To-Return Zone in Fukushima 更正:在福岛难以返回的地区发布疏散令时，空气中放射性铯快速检测系统的演示

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/TAESJ.J18.024E

T. Maekawa, Y. Oshima

引用次数: 0

Seven-year Temporal Variation of Cesium-137 Discharge Inventory from the Port of Fukushima Dai-ichi Nuclear Power Plant: 福岛第一核电站港口铯-137排放清单的7年时间变化

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/taesj.j18.030

M. Machida, S. Yamada, Ayako Iwata, S. Otosaka, Takuya Kobayashi, Masahisa Watababe, H. Funasaka, T. Morita

引用次数: 3