Journal of the Nuclear Fuel Cycle and Waste Technology最新文献_第5页

The Assessment of Exposure Dose of Radiation Workers for Decommissioning Waste in the Radioactive Waste Inspection Building of Low and Intermediate-Level Radioactive Waste Disposal Facility 中低放废物处置设施放射性废物检查楼退役废物辐射工作人员暴露剂量评估

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2020-08-30 DOI: 10.7733/jnfcwt.2020.18.2(e).317

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

{"title":"The Assessment of Exposure Dose of Radiation Workers for Decommissioning Waste in the Radioactive Waste Inspection Building of Low and Intermediate-Level Radioactive Waste Disposal Facility","authors":"Rin-Ah Kim, Dho Hoseog, K. T. man, C. Cho","doi":"10.7733/jnfcwt.2020.18.2(e).317","DOIUrl":"https://doi.org/10.7733/jnfcwt.2020.18.2(e).317","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 Korea Radioactive Waste Agency plans to expand the storage capacity of radioactive waste by constructing a radioactive waste inspecting building to solve the problem of the lack of inspection space and drum-handling space in the radioactive waste receipt and storage building for the first-stage disposal facility. In this study, the exposure doses of radiation workers that handle new disposal containers for decommissioning waste in the storage areas of the radioactive waste inspecting building were calculated using the Monte Carlo N-particle transport code. The annual collective dose was calculated as a total of 84.8 man-mSv for 304 new disposal containers and an estimated annual 306 working hours for the radiation work. When the 304 new disposal containers (small/medium type) were stored in the storage areas, it was found that 25 radiation workers should be involved in acceptance/disposal inspection, and the estimated exposure dose per worker was calculated as an average annual value of 3.39 mSv. When the radiation workers handle the small containers in high-radiation dose areas, the small containers should be shielded further by increasing the concrete liner thickness to improve the work efficiency and radiation safety of the radiation workers. The results of this study will be useful in establishing the optimal radiation working conditions for radiation workers using the source term and characteristics of decommissioning waste based on actual measurements.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2020-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80378363","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

Method for Evaluating Radionuclide Transport in Biosphere by Calculating Elapsed Transport Time 通过计算经过的传输时间来评估生物圈中放射性核素传输的方法

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2020-08-30 DOI: 10.7733/jnfcwt.2020.18.2(e).305

Nak-Youl Ko, S. Ji

引用次数: 0

Safety Evaluation of Clearance of Radioactive Metal Waste After Decommissioning of NPP 核电厂退役后放射性金属废物清理的安全性评价

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2020-08-30 DOI: 10.7733/jnfcwt.2020.18.2(e).291

Young-Hwan Choi, Jae-Hun Ko, Dong-gyu Lee, Young Hwan Hwang, Mihyeon Lee, Jihoon Lee, S. Hong

引用次数: 0

Data Analysis of International Joint Road and Sea Transportation Tests Under Normal Conditions of Transport 正常运输条件下国际道路和海上联合运输试验数据分析

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2020-08-30 DOI: 10.7733/jnfcwt.2020.18.2(e).275

Jaehoon Lim, S. Cho, W. Choi

引用次数: 1

Simulation Study on Atmospheric Emission Scenarios of Radioxenon Produced by the North Korea’s 6th Nuclear Test 朝鲜第六次核试验产生的放射性氙大气排放情景模拟研究

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2020-08-30 DOI: 10.7733/jnfcwt.2020.18.2(e).261

Kihyun Park, B. Min, Sora Kim, Kim Ji-Yoon, Suh Kyung Suk

{"title":"Simulation Study on Atmospheric Emission Scenarios of Radioxenon Produced by the North Korea’s 6th Nuclear Test","authors":"Kihyun Park, B. Min, Sora Kim, Kim Ji-Yoon, Suh Kyung Suk","doi":"10.7733/jnfcwt.2020.18.2(e).261","DOIUrl":"https://doi.org/10.7733/jnfcwt.2020.18.2(e).261","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 North Korea conducted the sixth underground nuclear test on September 3, 2017 at the Punggye-ri Nuclear Test Site (NTS). In contrast to the previous five nuclear tests, several induced earthquakes occurred around the NTS after the sixth nuclear test and this may have caused radioxenon leakages at the site. Considering these reported earthquakes, we performed atmospheric dispersion simulations on some radioxenon emission scenarios for this event using our Lagrangian Atmospheric Dose Assessment System (LADAS) model by employing the Unified Model (UM) based numerical weather prediction data produced by the Korea Meteorological Administration (KMA). To find out possible detection locations and times, we combined not only daily and weekly based delayed releases but also leakages after the reported earthquakes around the NTS to create emission scenarios. Our simulation results were generally in good agreement with the measured data of the Nuclear Safety and Security Commission and International Monitoring System (IMS) stations operated by the Comprehensive nuclear Test-Ban-Treaty Organization (CTBTO).","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2020-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74579120","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

Corrosion Behavior of Stainless Steel 316 for Carbon Anode Oxide Reduction Application 碳阳极氧化还原应用中316不锈钢的腐蚀行为

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2020-06-30 DOI: 10.7733/jnfcwt.2020.18.2.169

M. Jeon, Sung-Wook Kim, E. Choi

引用次数: 0

Modeling the Groundwater Flow in the Near-field of the Near-surface Disposal System 近地表处理系统近场地下水流动模拟

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2020-06-30 DOI: 10.7733/jnfcwt.2020.18.2.119

Jung-Woo Kim, J. Bang, D. Cho

{"title":"Modeling the Groundwater Flow in the Near-field of the Near-surface Disposal System","authors":"Jung-Woo Kim, J. Bang, D. Cho","doi":"10.7733/jnfcwt.2020.18.2.119","DOIUrl":"https://doi.org/10.7733/jnfcwt.2020.18.2.119","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 numerical model was developed using COMSOL Multiphysics to evaluate groundwater flow that causes radionuclide migration in the unsaturated zone of a near-surface disposal facility, which is considered as a domestic low and an intermediate-level radioactive waste disposal facility. Each scenario was modeled by constructing a two-dimensional domain that included the disposal vault, backfill, disposal cover, and unsaturated aquifer. A comparison of the continuous and intermittent rainfall conditions exhibited no significant difference in any of the factors considered except the wave pattern of water saturation. The input data, such as porosity and residual water content of the unsaturated aquifer, were observed to not have a significant effect on the groundwater flow. However, the hydraulic conductivity of the unsaturated aquifer was found to have a significant effect on the groundwater flow. Therefore, it is necessary to assess the hydraulic conductivity of an unsaturated aquifer to determine the extent of groundwater infiltration into the disposal vault.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2020-06-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83665620","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

A Prediction of Saturated Hydraulic Conductivity for Compacted Bentonite Buffer in a High-level Radioactive Waste Disposal System 高放废物处理系统中压实膨润土缓冲液饱和导电性的预测

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2020-06-30 DOI: 10.7733/jnfcwt.2020.18.2.133

S. Park, Seok Yoon, Sangki Kwon, Geon-Young Kim

{"title":"A Prediction of Saturated Hydraulic Conductivity for Compacted Bentonite Buffer in a High-level Radioactive Waste Disposal System","authors":"S. Park, Seok Yoon, Sangki Kwon, Geon-Young Kim","doi":"10.7733/jnfcwt.2020.18.2.133","DOIUrl":"https://doi.org/10.7733/jnfcwt.2020.18.2.133","url":null,"abstract":"A geological repository comprises a natural barrier and an engineered barrier system. Its design components consist of canisters, buffers, backfill, and near-field rock. Among the engineered barrier system components, bentonite buffers minimize the groundwater flow from near-field rock and prevent the release of nuclide. Investigation of the hydraulic conductivity of the buffer to groundwater flow is an important factor in the performance evaluation of the stability and integrity of the engineered barrier of the repository. In this study, saturated hydraulic conductivity tests were performed using Gyeongju bentonite at various dry densities and temperatures, and a hydraulic conductivity prediction model was developed through multiple regression analysis using the 120 result sets of hydraulic conductivity. The test results showed that the hydraulic conductivity tends to decrease as the dry density increases. In addition, the hydraulic conductivity increased with increasing temperature. The multiple regression analysis results showed that the coefficient of determination (R2) of the hydraulic conductivity prediction equation was as high as 0.93. The hydraulic conductivity prediction equation presented in this study could be used for the design of engineered barrier systems.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2020-06-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74197632","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

Internal Dose Assessment of Worker by Radioactive Aerosol Generated During Mechanical Cutting of Radioactive Concrete 放射性混凝土机械切割过程中产生的放射性气溶胶对工人的内剂量评估

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2020-06-30 DOI: 10.7733/jnfcwt.2020.18.2.157

Jihye Park, Wonseok Yang, Nakkyu Chae, Min-Ho Lee, Sungyeol Choi

引用次数: 1

Sequential Bayesian Updating Module of Input Parameter Distributions for More Reliable Probabilistic Safety Assessment of HLW Radioactive Repository 高放库更可靠概率安全评估输入参数分布的顺序贝叶斯更新模块

Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2020-06-30 DOI: 10.7733/jnfcwt.2020.18.2.179

Youn-Myoung Lee, D. Cho

{"title":"Sequential Bayesian Updating Module of Input Parameter Distributions for More Reliable Probabilistic Safety Assessment of HLW Radioactive Repository","authors":"Youn-Myoung Lee, D. Cho","doi":"10.7733/jnfcwt.2020.18.2.179","DOIUrl":"https://doi.org/10.7733/jnfcwt.2020.18.2.179","url":null,"abstract":"A Bayesian approach was introduced to improve the belief of prior distributions of input parameters for the probabilistic safety assessment of radioactive waste repository. A GoldSim-based module was developed using the Markov chain Monte Carlo algorithm and implemented through GSTSPA (GoldSim Total System Performance Assessment), a GoldSim template for generic/site-specific safety assessment of the radioactive repository system. In this study, sequential Bayesian updating of prior distributions was comprehensively explained and used as a basis to conduct a reliable safety assessment of the repository. The prior distribution to three sequential posterior distributions for several selected parameters associated with nuclide transport in the fractured rock medium was updated with assumed likelihood functions. The process was demonstrated through a probabilistic safety assessment of the conceptual repository for illustrative purposes. Through this study, it was shown that insufficient observed data could enhance the belief of prior distributions for input parameter values commonly available, which are usually uncertain. This is particularly applicable for nuclide behavior in and around the repository system, which typically exhibited a long time span and wide modeling domain.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2020-06-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83818847","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