Journal of the Nuclear Fuel Cycle and Waste Technology最新文献_第2页

A Study on the Evaluation of Surface Dose Rate of New Disposal Containers Though the Activation Evaluation of Bio-Shield Concrete Waste From Kori Unit 1 Kori 1号机组生物屏蔽混凝土废弃物活化评价新处置容器表面剂量率的研究

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2021-03-31 DOI: 10.7733/JNFCWT.2021.19.1.133

Gi-Woong Kang, Rin-Ah Kim, Dho Hoseog, K. T. man, C. Cho

{"title":"A Study on the Evaluation of Surface Dose Rate of New Disposal Containers Though the Activation Evaluation of Bio-Shield Concrete Waste From Kori Unit 1","authors":"Gi-Woong Kang, Rin-Ah Kim, Dho Hoseog, K. T. man, C. Cho","doi":"10.7733/JNFCWT.2021.19.1.133","DOIUrl":"https://doi.org/10.7733/JNFCWT.2021.19.1.133","url":null,"abstract":"This is an Open-Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/ by-nc/3.0) which permits unrestricted non-commercial use, distribution, and reproduction in any medium, provided the original work is properly cited This study evaluates the radioactivity of concrete waste that occurs due to large amounts of decommissioned nuclear wastes and then determines the surface dose rate when the waste is packaged in a disposal container. The radiation assessment was conducted under the presumption that impurities included in the bio-shielded concrete contain the highest amount of radioactivity among all the concrete wastes. Neutron flux was applied using the simplified model approach in a sample containing the most Co and Eu impurities, and a maximum of 9.8×104 Bq·g−1 60Co and 2.63×105 Bq·g−1 152Eu was determined. Subsequently, the surface dose rate of the container was measured assuming that the bio-shield concrete waste would be packaged in a newly developed disposal container. Results showed that most of the concrete wastes with a depth of 20 cm or higher from the concrete surface was found to have less than 1.8 mSv·hr−1 in the surface dose of the new-type disposal container. Hence, when bio-shielded concrete wastes, having the highest radioactivity, is disposed in the new disposal container, it satisfies the limit of the surface dose rate (i.e., 2 mSv·hr−1) as per global standards.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74657522","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

A Study About Radionuclides Migration Behavior in Terms of Solubility at Gyeongju Low- and Intermediate-Level Radioactive Waste (LILW) Repository 庆州中低放废物处置库放射性核素溶解度迁移行为研究

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2021-03-31 DOI: 10.7733/JNFCWT.2021.19.1.113

Park Sang June, Jihyang Byon, Lee, Jun-Yeop, Seokyoung Ahn

引用次数: 0

Flow Characteristics Analysis for the Chemical Decontamination of the Kori-1 Nuclear Power Plant 高丽1号核电站化学净化的流动特性分析

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2021-03-31 DOI: 10.7733/JNFCWT.2021.19.1.51

Seo-yeon Cho, Byong-Woo Kim, Bang, Youngsuk, Keon-Yeop Kim

{"title":"Flow Characteristics Analysis for the Chemical Decontamination of the Kori-1 Nuclear Power Plant","authors":"Seo-yeon Cho, Byong-Woo Kim, Bang, Youngsuk, Keon-Yeop Kim","doi":"10.7733/JNFCWT.2021.19.1.51","DOIUrl":"https://doi.org/10.7733/JNFCWT.2021.19.1.51","url":null,"abstract":"This is an Open-Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/ by-nc/3.0) which permits unrestricted non-commercial use, distribution, and reproduction in any medium, provided the original work is properly cited Chemical decontamination of primary systems in a nuclear power plant (NPP) prior to commencing the main decommissioning activities is required to reduce radiation exposure during its process. The entire process is repeated until the desired decontamination factor is obtained. To achieve improved decontamination factors over a shorter time with fewer cycles, the appropriate flow characteristics are required. In addition, to prepare an operating procedure that is adaptable to various conditions and situations, the transient analysis results would be required for operator action and system impact assessment. In this study, the flow characteristics in the steady-state and transient conditions for the chemical decontamination operations of the Kori-1 NPP were analyzed and compared via the MARS-KS code simulation. Loss of residual heat removal (RHR) and steam generator tube rupture (SGTR) simulations were conducted for the postulated abnormal events. Loss of RHR results showed the reactor coolant system (RCS) temperature increase, which can damage the reactor coolant pump (RCP)s by its cavitation. The SGTR results indicated a void formation in the RCS interior by the decrease in pressurizer (PZR) pressure, which can cause surface exposure and tripping of the RCPs unless proper actions are taken before the required pressure limit is achieved.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83416117","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: 3

Data-Driven Modelling of Damage Prediction of Granite Using Acoustic Emission Parameters in Nuclear Waste Repository 基于声发射参数的核废料库花岗岩损伤预测数据驱动模型

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2021-03-31 DOI: 10.7733/JNFCWT.2021.19.1.75

Hang-Lo Lee, Jin-Seop Kim, Chang-Ho Hong, Ho-Young Jeong, D. Cho

引用次数: 0

Development of New Processes for the Decommissioning Decontamination and for Treatment and Disposal of the Secondary Low- and Intermediate-Level Radioactive Waste 中低放射性二级废物的退役、净化和处理处置新工艺的发展

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2021-03-31 DOI: 10.7733/JNFCWT.2021.19.1.9

J. John, P. Bartl, Kateřina Čubová, M. Němec, M. Semelová, F. Šebesta, Tereza Šobová, J. Šuľaková, A. Vetešník, D. Vopálka

{"title":"Development of New Processes for the Decommissioning Decontamination and for Treatment and Disposal of the Secondary Low- and Intermediate-Level Radioactive Waste","authors":"J. John, P. Bartl, Kateřina Čubová, M. Němec, M. Semelová, F. Šebesta, Tereza Šobová, J. Šuľaková, A. Vetešník, D. Vopálka","doi":"10.7733/JNFCWT.2021.19.1.9","DOIUrl":"https://doi.org/10.7733/JNFCWT.2021.19.1.9","url":null,"abstract":"This is an Open-Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/ by-nc/3.0) which permits unrestricted non-commercial use, distribution, and reproduction in any medium, provided the original work is properly cited As an example of research activities in decontamination for decommissioning, new data are presented on the options for corrosion layer dissolution during the decommissioning decontamination, or persulfate regeneration for decontamination solutions re-use. For the management of spent decontamination solutions, new method based on solvent extraction of radionuclides into ionic liquid followed by electrodeposition of the radionuclides has been developed. Fields of applications of composite inorganic-organic absorbers or solid extractants with polyacrylonitrile (PAN) binding matrix for the treatment of liquid radioactive waste are reviewed; a method for americium separation from the boric acid containing NPP evaporator concentrates based on the TODGA-PAN material is discussed in more detail. Performance of a model of radionuclide transport, developed and implemented within the GoldSim programming environment, for the safety studies of the LLW/ILW repository is demonstrated on the specific case of the Richard repository (Czech Republic). Continuation and even broadening of these activities are expected in connection with the approaching end of the lifespan of the first blocks of the Czech NPPs.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85419973","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

Application of Logistic Simulation for Transport of SFs From Kori Site to an Assumed Interim Storage Facility 从Kori站点到假定的临时存储设施运输的物流模拟应用

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2021-03-31 DOI: 10.7733/JNFCWT.2021.19.1.61

Young-Min Kim, Chang-Lak Kim

{"title":"Application of Logistic Simulation for Transport of SFs From Kori Site to an Assumed Interim Storage Facility","authors":"Young-Min Kim, Chang-Lak Kim","doi":"10.7733/JNFCWT.2021.19.1.61","DOIUrl":"https://doi.org/10.7733/JNFCWT.2021.19.1.61","url":null,"abstract":"This is an Open-Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/ by-nc/3.0) which permits unrestricted non-commercial use, distribution, and reproduction in any medium, provided the original work is properly cited A paradigm shift in the government’s energy policy was reflected in its declaration of early closure of old nuclear plants as well as cancellation of plans for the construction of new plants. To this end, unit 1 of Kori Nuclear Power Plant was permanently shut down and is set for decommission. Based on these changes, the off-site transport of spent fuels from nuclear power plants has become a critical issue. The purpose of this study is to develop an optimized method for transportation of spent fuels from Kori Nuclear Power Plant’s units 1, 2, 3, and 4 to an assumed interim storage facility by simulating the scenarios using the Flexsim software, which is widely used in logistics and manufacturing applications. The results of the simulation suggest that the optimized transport methods may contribute to the development of delivery schedule of spent fuels in the near future. Furthermore, these methods can be applied to decommissioning plan of nuclear power plants.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91480516","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

Sorption of Np(IV) on MX-80 in Ca-Na-Cl Type Reference Water of Crystalline Rock MX-80在结晶岩Ca-Na-Cl型基准水中对Np(IV)的吸附

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2021-03-31 DOI: 10.7733/JNFCWT.2021.19.1.1

S. Nagasaki

{"title":"Sorption of Np(IV) on MX-80 in Ca-Na-Cl Type Reference Water of Crystalline Rock","authors":"S. Nagasaki","doi":"10.7733/JNFCWT.2021.19.1.1","DOIUrl":"https://doi.org/10.7733/JNFCWT.2021.19.1.1","url":null,"abstract":"This is an Open-Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/ by-nc/3.0) which permits unrestricted non-commercial use, distribution, and reproduction in any medium, provided the original work is properly cited The pH dependence of sorption distribution coefficient (Kd) of Np(IV) on MX-80 in Ca-Na-Cl type solution with the ionic strength of 0.3 M, which was similar to one of the reference groundwaters in crystalline rock, was experimentally investigated under the reducing conditions. The overall trend of Kd on MX-80 was independent of pH at 5 ≤ pH ≤ 10 but increased as pH increased at pH ≤ 5. The 2-site protolysis non-electrostatic surface complexation and cation exchange model was applied to the experimentally measured pH dependence of Kd and the optimized surface complexation constants of Np(IV) sorption on MX-80 were estimated. The values of surface complexation constants in this work agreed relatively well with those in the Na-Ca-Cl solution previously evaluated, suggesting that compared to Na+, the competition of Ca2+ with Np(IV) for surface complexation on MX-80 was not much strong in Ca-Na-Cl solution. The sorption model well predicted the pH dependence of Kd values but slightly overestimated the sorption at the low pH region.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76148668","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

Preparation of the Applicable Regulatory Guideline on Mixed Waste in Korea Based on the Analysis of US Laws and Regulations 基于美国法律法规分析的韩国混合废物适用监管指南的制定

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2021-03-31 DOI: 10.7733/JNFCWT.2021.19.1.141

Eun-Jin Sim, Sun-Kee Lee, Chang-Lak Kim, Tae-Man Kim

引用次数: 0

Radiological Safety Assessment for a Near-Surface Disposal Facility Using RESRAD-ONSITE Code 使用resrad - site规范进行近地表处置设施辐射安全评估

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2021-03-31 DOI: 10.7733/JNFCWT.2021.19.1.123

Jiseon Jang, Tae-Man Kim, C. Cho, D. Lee

{"title":"Radiological Safety Assessment for a Near-Surface Disposal Facility Using RESRAD-ONSITE Code","authors":"Jiseon Jang, Tae-Man Kim, C. Cho, D. Lee","doi":"10.7733/JNFCWT.2021.19.1.123","DOIUrl":"https://doi.org/10.7733/JNFCWT.2021.19.1.123","url":null,"abstract":"This is an Open-Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/ by-nc/3.0) which permits unrestricted non-commercial use, distribution, and reproduction in any medium, provided the original work is properly cited Radiological impact analyses were carried out for a near-surface radioactive waste repository at Gyeongju in South Korea. The RESRAD-ONSITE code was applied for the estimation of maximum exposure doses by considering various exposure pathways based on a land area of 2,500 m2 with a 0.15 m thick contamination zone. Typical influencing input parameters such as shield depth, shield materials’ density, and shield erosion rate were examined for a sensitivity analysis. Then both residential farmer and industrial worker scenarios were used for the estimation of maximum exposure doses depending on exposure duration. The radiation dose evaluation results showed that 60Co, 137Cs, and 63Ni were major contributors to the total exposure dose compared with other radionuclides. Furthermore, the total exposure dose from ingestion (plant, meat, and milk) of the contaminated plants was more significant than those assessed for inhalation, with maximum values of 5.5×10−4 mSv‧yr−1 for the plant ingestion. Thus the results of this study can be applied for determining near-surface radioactive waste repository conditions and providing quantitative analysis methods using RESRAD-ONSITE code for the safety assessment of disposing radioactive materials including decommissioning wastes to protect human health and the environment.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89784786","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: 5

Status of Czech Low and Intermediate Radioactive Waste Management in the Context of European Development 欧洲发展背景下捷克中低放射性废物管理的现状

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2021-03-31 DOI: 10.7733/JNFCWT.2021.19.1.29

R. Trtílek, V. Havlová, J. Podlaha, K. Svoboda, Tomas Otcovský

引用次数: 0