Atomic Energy Society of Japan最新文献_第5页

Quantitative Analysis of Japan’s Energy Security based on Fuzzy Logic 基于模糊逻辑的日本能源安全定量分析

Atomic Energy Society of Japan Pub Date : 2017-01-23 DOI: 10.1155/2017/4865913

R. Yamanishi

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引用次数: 4

Performances of Molten-Salt Fast Reactor with Self-Sustainability 自持熔盐快堆性能研究

Atomic Energy Society of Japan Pub Date : 2017-01-01 DOI: 10.3327/TAESJ.J16.029

K. Mitachi

{"title":"Performances of Molten-Salt Fast Reactor with Self-Sustainability","authors":"K. Mitachi","doi":"10.3327/TAESJ.J16.029","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.029","url":null,"abstract":"A study is performed on a molten salt fast reactor （ MSFR ） of 1.5 GWe output. The reactor is started up by using transuranium elements reprocessed from spent fuel of a BWR. The fuel salt of the reactor is the mixed ﬂuoride salt NaF – KF – UF 4 – TRUF 3 , which is reprocessed almost continuously by an oxide-precipitation process during the reactor operation. By performing calculations using the nuclear analysis code PIJ – BURN in SRAC2006 and the nuclear data ﬁle of JENDL – 3.3, the following re-sults are obtained. （ 1 ） The burn-up characteristics of the reactor are mainly determined by the uranium inventory （ U inv ） in the reactor and the reprocessing cycle （ L rep ） , which is the time interval necessary to reprocess all the fuel salt in the primary loop. （ 2 ） A large U inv and short L rep enhance the breeding performance of the reactor. （ 3 ） The period necessary to keep the radioactive waste under control will be about 400 years in the case of L rep longer than 400 efpd. （ 4 ） Power stations consisting of 20 MSFRs （ total output of 30 GWe ） can operate for 600 years by utilizing 14,000 t of uranium obtained from the spent fuel of LWRs in Japan.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"13 1","pages":"173-179"},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85249511","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

Preparation of Sodium Uranates 铀酸钠的制备

Atomic Energy Society of Japan Pub Date : 2017-01-01 DOI: 10.3327/TAESJ.J16.035

Masayoshi Uno, K. Yokoyama, Y. Murakami

引用次数: 0

Evaluation of Ambient Dose Equivalent Rates Owing to Natural Radioactive Nuclides in Eastern Japan by Car-Borne Surveys Using KURAMA–II 利用KURAMA-II车载调查评估日本东部天然放射性核素的环境剂量当量率

Atomic Energy Society of Japan Pub Date : 2017-01-01 DOI: 10.3327/TAESJ.J16.023

M. Andoh, N. Matsuda, Kimiaki Saito

引用次数: 21

Proposal of Methodology of Tsunami Accident Sequence Analysis Induced by Earthquake Using DQFM Methodology 基于DQFM方法的地震海啸事故序列分析方法的提出

Atomic Energy Society of Japan Pub Date : 2017-01-01 DOI: 10.3327/TAESJ.J16.019

H. Muta, K. Muramatsu

引用次数: 1

Evaluation of Atmospheric-Pressure Change in Tornado Using Fujita Model 用Fujita模式评价龙卷风的气压变化

Atomic Energy Society of Japan Pub Date : 2017-01-01 DOI: 10.3327/TAESJ.J16.009

Juntaro Shimizu, Shunsuke Ohtsubo

{"title":"Evaluation of Atmospheric-Pressure Change in Tornado Using Fujita Model","authors":"Juntaro Shimizu, Shunsuke Ohtsubo","doi":"10.3327/TAESJ.J16.009","DOIUrl":"https://doi.org/10.3327/TAESJ.J16.009","url":null,"abstract":"Evaluation of the atmospheric-pressure change （ APC ） in a tornado is necessary to assess the integrity of nuclear-related facilities. The Rankine model has been most frequently used to theoretically calculate the APC in a tornado. The result, however, is considered to be overly conservative because the Rankine model wind speed at the ground is larger than that in reality. On the other hand, the wind speed of the Fujita model is closer to that of actual tornadoes but is expressed by more complicated algebraic equations than that in the Rankine model. Also, because it is impossible to analytical-ly derive the APC equation using the Fujita model, numerical computation is required. A previous study employed the ﬁnite element method （ FEM ） for such a purpose. However, a general-purpose FEM code often requires complicated input parameters. In order to conduct parametric studies to evaluate the integrity of facilities in various cases of tornadoes, the ﬁnite-difference method code “TORPEC”, which is specialized to analyze the APC, was developed as a convenient design tool. TORPEC is based on Poisson’s equation derived from the Navier-Stokes equation. It also runs on widely available technical calculation software such as Microsoft ® Excel VBA or MATLAB ® . Taking advantage of such convenience, various calculations have been conducted to reveal the characteristics of APC as functions of the maximum tangential wind speed, axial position and tornado radius. TORPEC is used as a benchmark in the existing paper. The case study results obtained by TORPEC show a constant ratio of the pressure drop of the Fujita model against the Rankine model. This factor can be used to derive the Fujita model result from the Rankine model result without FEM analysis.","PeriodicalId":8595,"journal":{"name":"Atomic Energy Society of Japan","volume":"18 1","pages":"81-88"},"PeriodicalIF":0.0,"publicationDate":"2017-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79185425","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

Differences in opinions on nuclear power generation between Japanese and Korean university students 日本和韩国大学生对核能发电的不同看法

Atomic Energy Society of Japan Pub Date : 2017-01-01 DOI: 10.3327/TAESJ.J16.016

Yuka Watanabe, K. Kudo, K. Idemitsu

引用次数: 0

A Study on Enhancing the Effectiveness of Safety Culture in Nuclear Power Plants 提高核电厂安全文化有效性的研究

Atomic Energy Society of Japan Pub Date : 2017-01-01 DOI: 10.3327/TAESJ.J16.002

A. Yamamoto, N. Sekimura

引用次数: 0

Temperature Measurement of Control Rod Using Melt Wire in High-Temperature Engineering Test Reactor (HTTR) 高温工程试验堆(HTTR)控制棒用熔体丝测温

Atomic Energy Society of Japan Pub Date : 2017-01-01 DOI: 10.3327/TAESJ.J16.036

S. Hamamoto, D. Tochio, T. Ishii, Hiroaki Sawahata

引用次数: 1

Design and Construction plan of Spent Fuel Removal Structure for Fukushima Daiichi Nuclear Power Station Unit 3 福岛第一核电站3号机组乏燃料清除结构设计与施工方案

Atomic Energy Society of Japan Pub Date : 2017-01-01 DOI: 10.3327/JAESJB.59.1_23

I. Matsuo

引用次数: 0