Transactions of the Atomic Energy Society of Japan最新文献_第6页

Irradiation Growth Behavior of Improved Alloys for Fuel Cladding 燃料包壳用改进合金的辐照生长行为

Transactions of the Atomic Energy Society of Japan Pub Date : 2020-01-01 DOI: 10.3327/taesj.j18.047

K. Kakiuchi, M. Amaya

{"title":"Irradiation Growth Behavior of Improved Alloys for Fuel Cladding","authors":"K. Kakiuchi, M. Amaya","doi":"10.3327/taesj.j18.047","DOIUrl":"https://doi.org/10.3327/taesj.j18.047","url":null,"abstract":"New Zr alloys for fuel cladding with different compositions from conventional ones have been de-veloped to increase the safety of nuclear power plants and to utilize existing nuclear power plants more effectively. Since the irradiation growth of fuel cladding is one of the most important parameters regarding the dimensional stability of a fuel rod and / or fuel assembly during irradiation, the irradiation growth behavior of the improved Zr alloys for light-water reactor fuel cladding was investigated. Coupon specimens, which were prepared from fuel cladding tubes with improved Zr alloys, were irra-diated in the Halden reactor in Norway at temperatures of 300 and 320 ℃ under a typical water chem-istry condition of a PWR and at 240 ℃ under the coolant condition of the Halden reactor up to a fast neutron ﬂuence of ～ 8 × 10 25 （ 1 / m 2 , E ＞ 1 MeV ） . During and after the irradiation test, the amount of irradiation growth of each specimen was evaluated. The effect of the difference in alloy composition on irradiation growth behavior seemed insigniﬁcant if the other conditions, such as the ﬁnal heat treat ment condition at fabrication, the irradiation temperature and the amount of hydrogen precharged in the specimen, were the same.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437503","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

Evaluation of Dose Equivalent Rates for a New Exclusive Ship “Seiei Maru” for Transporting Low-Level Radioactive Waste by Monte Carlo Particle Transport Calculation Using Variance Reduction Parameter Derived by FW-CADIS Method 用w- cadis法推导方差约化参数的蒙特卡罗粒子输运计算方法评估用于运输低放射性废物的新型专用船“清明丸”的剂量当量率

Transactions of the Atomic Energy Society of Japan Pub Date : 2020-01-01 DOI: 10.3327/taesj.j19.024

M. Asami, S. Ohnishi, S. Kamada

{"title":"Evaluation of Dose Equivalent Rates for a New Exclusive Ship “Seiei Maru” for Transporting Low-Level Radioactive Waste by Monte Carlo Particle Transport Calculation Using Variance Reduction Parameter Derived by FW-CADIS Method","authors":"M. Asami, S. Ohnishi, S. Kamada","doi":"10.3327/taesj.j19.024","DOIUrl":"https://doi.org/10.3327/taesj.j19.024","url":null,"abstract":"The forward weighted consistent adjoint driven importance sampling (FW-CADIS) method has been proposed as a method for obtaining variance reduction parameters to estimate flux or dose rate distribution over a wide area, or responses at multiple localized detectors for a particle transport calculation based on the stochastic Monte Carlo method with a reasonable and high accuracy. The method has been applied to estimating the dose equivalent rate around the Japanese exclusive ship, “Seiei Maru”, which transports low-level radioactive waste. The particle transport calculation was performed using a mesh tally on the entire surface of the hatch cover above low-level radioactive waste packages stacked in the cargo hold and point detector tallies at each measurement point. The statistical error is spatially uniform for the mesh tally and is reduced only around the vicinity of each point detector tally. It is suggested that the estimated dose equivalent rate obtained by the calculation is equivalent to the measured result, and it is shown that this method is effective for the radiation safety evaluation of low-level radioactive waste transport ships.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437353","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

Quantification of Radionuclide Migration Parameters in Safety Assessment of Radioactive Waste Disposal: Review on the Use of Expert Elicitation 放射性废物处置安全评价中放射性核素迁移参数的量化:专家启发法的应用综述

Transactions of the Atomic Energy Society of Japan Pub Date : 2020-01-01 DOI: 10.3327/taesj.j19.004

R. Nakabayashi, D. Sugiyama

{"title":"Quantification of Radionuclide Migration Parameters in Safety Assessment of Radioactive Waste Disposal: Review on the Use of Expert Elicitation","authors":"R. Nakabayashi, D. Sugiyama","doi":"10.3327/taesj.j19.004","DOIUrl":"https://doi.org/10.3327/taesj.j19.004","url":null,"abstract":"Expert elicitation has traditionally been accepted in some countries as a way to quantify the uncertainty of radionuclide migration parameters in the safety assessment of radioactive waste disposal. However, expert elicitation has not yet been explicitly performed in the field of radioactive waste disposal in Japan. To discuss the applicability of expert elicitation in Japan, here we broadly review the histories and methodologies of expert elicitation in some papers and review in more detail case studies on the utilization of expert elicitation in the safety assessment of radioactive waste disposal in the US, UK, and Sweden. From the literature review, we suggest that it is valuable to adopt expert elicitation to quantify the uncertainty of parameters in Japan. In particular, the documentation of each elicitation step is critical to ensuring the traceability and transparency of expert elicitation. The documentation enables the regulator to evaluate whether the expert judgment including the elicitation process is adequate. Furthermore, we recommend providing not only an aggregated expert judgment for safety assessment but also the distribution of individual expert judgements. Individual expert judgments will be used for related analyses (e.g., sensitivity or uncertainty analyses), leading to increased confidence in the safety assessment.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437081","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

Experiments of Self-wastage Phenomena Elucidation in Steam Generator Tube of Sodium-cooled Fast Reactor 钠冷快堆蒸汽发生管自耗现象的实验研究

Transactions of the Atomic Energy Society of Japan Pub Date : 2020-01-01 DOI: 10.3327/taesj.j19.012

Ryota Umeda, K. Shimoyama, A. Kurihara

{"title":"Experiments of Self-wastage Phenomena Elucidation in Steam Generator Tube of Sodium-cooled Fast Reactor","authors":"Ryota Umeda, K. Shimoyama, A. Kurihara","doi":"10.3327/taesj.j19.012","DOIUrl":"https://doi.org/10.3327/taesj.j19.012","url":null,"abstract":"The sodium – water reaction caused by failure of the steam generator tube of sodium-cooled fast re-actors causes the wastage phenomenon, which is erosive and corrosive. Self-wastage takes place in the early stage of the sodium – water reaction event when a very small amount of water / steam penetrates a microcrack. When self-wastage proceeds to the inside wall of the tube, the failed area and water leakage rate will increase, whereby the area affected by the sodium – water reaction will be likely to ex-tend. Thus, it is very important to clarify the self-wastage behavior for a locally affected region and detect water leakage in actual nuclear power plants. In this study, the authors performed self-wastage experiments under a high sodium temperature condition to evaluate the effects of the wastage form / geometry using two types of initial defect, i.e., the microﬁne pinhole and fatigue crack, and of the water leakage rate on the self-wastage rate. Taking into consideration the inﬂuence of crack type, we conﬁrmed that the self-wastage rate did not strongly depend on the initial defect geometry. As a mechanism of the self-plug phenomenon, it is speculated that sodium oxide blocks and inhibits the progress of self-wastage. The dependence of the self-wastage rate on the initial sodium temperature was clearly observed, and a new self-wastage correlation was derived considering the initial sodium temperature.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437141","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

Direct and Selective Electrodeposition of Palladium from Betainium Bis(trifluoromethanesulfonyl)imide Ionic Liquid Phase after Solvent Extraction together with Other Platinum Group Metals 溶剂萃取双(三氟甲烷磺酰)亚胺离子液相与其他铂族金属直接选择性电沉积钯

Transactions of the Atomic Energy Society of Japan Pub Date : 2020-01-01 DOI: 10.3327/taesj.j19.001

Soma Kono, Koichiro Takao, T. Arai

引用次数: 2

Feasibility of Disassembly of Fast Reactor Fuel Assembly Using Fiber Laser Cutting Technology 光纤激光切割技术拆卸快堆燃料组件的可行性

Transactions of the Atomic Energy Society of Japan Pub Date : 2020-01-01 DOI: 10.3327/taesj.j19.006

Hidetsugu Nishikawa, M. Takeuchi, T. Kitagaki, Shuho Tsubota, Yuuichi Tooya, I. Sato

引用次数: 0

Status of Investigation to Ensure Applicability of ECCS Acceptance Criteria to High-Burnup Fuel 确保ECCS验收标准适用于高燃耗燃料的研究现状

Transactions of the Atomic Energy Society of Japan Pub Date : 2020-01-01 DOI: 10.3327/taesj.j19.020

M. Ozawa, M. Amaya

{"title":"Status of Investigation to Ensure Applicability of ECCS Acceptance Criteria to High-Burnup Fuel","authors":"M. Ozawa, M. Amaya","doi":"10.3327/taesj.j19.020","DOIUrl":"https://doi.org/10.3327/taesj.j19.020","url":null,"abstract":"Light-water reactors (LWRs) are equipped with an emergency core cooling system (ECCS) that is designed to maintain the coolable geometry of the reactor core and finally minimize the release of radioactive fission products to the public and environment even in a loss-of-coolant accident (LOCA). Acceptance criteria for the ECCS of LWRs were determined to evaluate the safety function and performance in the design and to ensure a sufficient safety margin in the results of the evaluation. The latest revision of the criteria was made in 1981 in Japan, referring to the additional knowledge obtained after the previous revision. Fuel burnup has been extended by changing cladding materials, fuel design, etc., since the latest revision. Correspondingly, knowledge has been accumulated through studies on high-burnup fuel behavior under LOCA conditions to confirm the safety during the LOCA. This paper is a summary of the investigation and remaining issues on the applicability of the current Japanese ECCS acceptance criteria to high-burnup fuel, considering the history and basis of the current acceptance criteria. Results of the investigation conducted up to now reveal that the influence of burnup extension is small in terms of the cladding behavior of high-temperature oxidation and the fracture limit in quenching during the LOCA condition, and the current criteria are applicable even in the case of high-burnup fuel.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437310","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

Interaction of Liquid CsIO3 with a Polycrystalline UO2 Solid Surface 液态CsIO3与多晶UO2固体表面的相互作用

Transactions of the Atomic Energy Society of Japan Pub Date : 2020-01-01 DOI: 10.3327/taesj.j19.017

H. Ishii, Y. Ohishi, H. Muta, M. Uno, K. Kurosaki

引用次数: 0

Analytical Functions and Development Status of the System Analysis Code for Nuclear Power Plants, AMAGI 核电厂系统分析代码(AMAGI)的分析功能与发展现状

Transactions of the Atomic Energy Society of Japan Pub Date : 2020-01-01 DOI: 10.3327/taesj.j19.008

J. Kaneko, Naofumi Tsukamoto

引用次数: 1

Safety Function Reliability Evaluation and Risk Management during Decommissioning of Accident-Damaged Nuclear Power Plant ～Based on Results of Confinement Function Reliability Evaluation～基于约束功能可靠性评估结果的事故损坏核电站退役安全功能可靠性评估与风险管理

Transactions of the Atomic Energy Society of Japan Pub Date : 2020-01-01 DOI: 10.3327/taesj.j19.003

T. Aoki, Junya Masuko, Atsuo Ikeda, T. Negishi

引用次数: 0