Transactions of the Atomic Energy Society of Japan最新文献_第9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 (1st Report: Development of Analysis Method, Model Construction and Verification of Analysis Performance) 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(第一期报告:分析方法发展、模型构建及分析性能验证)

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/TAESJ.J18.001

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 (1st Report: Development of Analysis Method, Model Construction and Verification of Analysis Performance)","authors":"S. Yoshimura, T. Miyamura, Tomonori Yamada, H. Akiba, H. Kiyoura","doi":"10.3327/TAESJ.J18.001","DOIUrl":"https://doi.org/10.3327/TAESJ.J18.001","url":null,"abstract":"This research presents the recent development of the analysis system ADVENTURE, i.e., a parallel structural analysis solver ADVENTURE_Solid Ver.2 and its pre- / post-modules, towards petascale computers such as the K computer with 10 petaﬂops peak performance, as well as its application to 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 the Fukushima-Daiichi Nuclear Power Plant sub-jected to the 2011 off the Paciﬁc coast of Tohoku Earthquake of 9.0 Mw occurring on March 11, 2011. Here, we precisely modeled its pressure vessel, containment vessel, suppression chamber, vent piping, a number of supports and the reactor building with a 200 million DOF ﬁnite element mesh. Then, we successfully solved its dynamic response in 65 s. We report our research results in two papers, i.e., Part I and Part II. Part I （ this paper ） reports the developed analysis method, model construction, veriﬁcation of the analysis model, and computation performance. Part II reports the results of an eigen-analysis and a seismic response analysis. 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":"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.J18.001","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437270","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

Enhancing Emergency Response in the Field Based on Analysis of Workload Distribution at Fukushima Daiichi Nuclear Power Station 基于福岛第一核电站负荷分配分析的现场应急响应强化

Transactions of the Atomic Energy Society of Japan Pub Date : 2019-01-01 DOI: 10.3327/TAESJ.J18.041

Atsufumi Yoshizawa, K. Oba, M. Kitamura

引用次数: 0

Coupled Analysis of Fuel Debris Distribution and Recriticality by both Multiphase/Multicomponent Flow and Continuous Energy Neutron Transport Monte Carlo Simulations 多相/多组分流和连续能量中子输运蒙特卡罗模拟对燃料碎片分布和再临界性的耦合分析

Transactions of the Atomic Energy Society of Japan Pub Date : 2018-12-01 DOI: 10.3327/TAESJ.J17.026

S. Yamashita, Kenichi Tada, H. Yoshida, K. Suyama

{"title":"Coupled Analysis of Fuel Debris Distribution and Recriticality by both Multiphase/Multicomponent Flow and Continuous Energy Neutron Transport Monte Carlo Simulations","authors":"S. Yamashita, Kenichi Tada, H. Yoshida, K. Suyama","doi":"10.3327/TAESJ.J17.026","DOIUrl":"https://doi.org/10.3327/TAESJ.J17.026","url":null,"abstract":"To reveal the melting behaviors of core internals mechanistically and to reduce the uncertainties of existing severe accident analysis codes, a numerical simulation code for melt relocation and accumulation behaviors based on computational ﬂuid dynamics named JUPITER has been developed by JAEA. In this paper, we performed a simulation of the accumulation and spreading of a melt to the pedestal region of a typical BWR containment vessel by JUPITER to consider a method for estimating the fuel debris composition. We performed recriticality analysis by the continuous energy neutron transport Monte Carlo code MVP using detailed fuel debris composition data obtained by JUPITER to evaluate recriticality for fuel debris. It was revealed that JUPITER has the potential to obtain a com-plicated fuel debris distribution mechanistically. Also, in effective multiplication factor analyses, we investigated the effect of parameters （ uranium enrichment, water content ratio and partitioning resolution in MVP analysis ） on the effective multiplication factor. It was also revealed that the partitioning resolution is one of the most important factors in JUPITER-MVP coupled analysis, and an appro-priate partitioning according to the inhomogeneity of the fuel debris distribution obtained by JUPITER will be very important.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46621314","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

Synthesis and Characterization of CeO2-Based Simulated Fuel Containing CsI 含CsI的CeO2基模拟燃料的合成与表征

Transactions of the Atomic Energy Society of Japan Pub Date : 2018-12-01 DOI: 10.3327/TAESJ.J17.025

Yukichi Takamatsu, H. Ishii, Y. Ohishi, H. Muta, S. Yamanaka, E. Suzuki, K. Nakajima, S. Miwa, M. Osaka, K. Kurosaki

{"title":"Synthesis and Characterization of CeO2-Based Simulated Fuel Containing CsI","authors":"Yukichi Takamatsu, H. Ishii, Y. Ohishi, H. Muta, S. Yamanaka, E. Suzuki, K. Nakajima, S. Miwa, M. Osaka, K. Kurosaki","doi":"10.3327/TAESJ.J17.025","DOIUrl":"https://doi.org/10.3327/TAESJ.J17.025","url":null,"abstract":"Following the accident at the Fukushima Daiichi Nuclear Power Plant in 2011, radioactive nu-clides caused serious contamination. In particular, cesium （ Cs ） and iodine （ I ） are the most important ﬁssion products （ FPs ） because they are easily released due to their high vapor pressure. However, their release behavior from nuclear fuels during the accident has not been clariﬁed. Understanding such behavior can contribute to improving the accuracy of the source term evaluation. Simulated nuclear fuels containing non-radioactive FPs can be used in laboratory experiments to understand such behavior. However, simulated nuclear fuels containing Cs and I are difﬁcult to synthesize because of their high volatility. Here, cerium dioxide （ CeO 2 ） -based simulated fuels containing cesium iodide （ CsI ） are synthesized by spark plasma sintering, allowing us to obtain bulk samples rapidly at low temperatures compared with those of conventional sintering methods. CeO 2 is used to simulate uranium dioxide （ UO 2 ） owing to its similar chemical and physical properties to those of UO 2 . The obtained simulated fuels are characterized by X-ray diffraction and scanning electron microscopy / energy dis-persive X-ray spectrometry. CsI is conﬁrmed to exist as small precipitates almost uniformly distribut-ed throughout the CeO 2 matrix. The optimized conditions to synthesize the simulated fuels are pro-posed.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.3327/TAESJ.J17.025","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45117633","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

東京都市大学原子力研究所における1.7 MVペレトロン・タンデム加速器システムの構築作業およびそれを通じた人材育成东京都市大学原子能研究所1.7 MV peretron串联加速器系统的构筑工作以及通过该系统的人才培养

Transactions of the Atomic Energy Society of Japan Pub Date : 2018-12-01 DOI: 10.3327/TAESJ.J17.021

尚人羽倉, 規託林崎, 孝文内山, 慶之小栗, 一志福田, 克則川崎, 保鳥山, 幸一持木, 往子岡田, 順河原林, 偉司三橋, 治明松浦

引用次数: 1

低温，低酸素および高pH条件下におけるZr-2.5 wt％Nb合金(ふげん圧力管)の腐食速度の算出低温、低氧及高pH值条件下Zr-2.5 wt % Nb合金(钝化压力管)腐蚀速度的计算

Transactions of the Atomic Energy Society of Japan Pub Date : 2015-01-01 DOI: 10.3327/TAESJ.J14.032R

圭一酒谷, 隆良中谷, 英之船橋

引用次数: 0