{"title":"Evaluation of Exposure Dose and Working Hours for Near Surface Disposal Facility","authors":"Yeseul Cho, H. Dho, H. Kang, C. Cho","doi":"10.7733/jnfcwt.2022.039","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.039","url":null,"abstract":"","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"68 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-12-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83265296","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}
S. Lee, Jin-Seok Kim, Bong-Ju Kim, Jae-Kwang Lee, Seung Yeop Lee, Jang-Soon Kwon
{"title":"International Joint Research for the Colloid Formation and Migration in Grimsel Test Site: Current Status and Perspectives","authors":"S. Lee, Jin-Seok Kim, Bong-Ju Kim, Jae-Kwang Lee, Seung Yeop Lee, Jang-Soon Kwon","doi":"10.7733/jnfcwt.2022.034","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.034","url":null,"abstract":"","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"96 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-12-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78339559","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}
Kyungwon Suh, Jung Bo Yoo, K. Choi, Gi-Yong Kim, Si-duk Oh, Kanghyun Yoo, Kwang Eun Lee, S. Lee, Young Sang Lee, Hyeju Lee, Junhyuck Kim, K. Jung, Sora Choi, T. Park
The decommissioning of nuclear facilities produces various types of radiologically contaminated waste. In addition, dismantlement activities, including cutting, packing, and clean-up at the facility site, result in secondary radioactive waste such as filters, resin, plastic, and clothing. Determining of the radionuclide content of this waste is an important step for the determination of a suitable management strategy including classification and disposal. In this work, we radiochemically characterized the radionuclide activities of filters used during the decommissioning of Korea Research Reactors (KRRs) 1 and 2. The results indicate that the filter samples contained mainly 3 H (500–3,600 Bq·g −1 ), 14 C (7.5–29 Bq·g −1 ), 55 Fe (1.1– 7.1 Bq·g −1 ), 59 Ni (0.60–1.0 Bq·g −1 ), 60 Co (0.74–70 Bq·g −1 ), 63 Ni (0.60–94 Bq·g −1 ), 90 Sr (0.25–5.0 Bq·g −1 ), 137 Cs (0.64–8.7 Bq·g −1 ), and 152 Eu (0.19–2.9
核设施的退役会产生各种受放射性污染的废物。此外，拆解活动，包括在设施现场切割、包装和清理，会产生二次放射性废物，如过滤器、树脂、塑料和衣服。确定这种废物的放射性核素含量是确定包括分类和处置在内的适当管理战略的重要步骤。在这项工作中，我们对韩国研究堆(KRRs) 1和2退役期间使用的过滤器的放射性核素活性进行了放射化学表征。结果表明:过滤样品主要含有3 H (500 ~ 3600 Bq·g−1)、14 C (7.5 ~ 29 Bq·g−1)、55 Fe (1.1 ~ 7.1 Bq·g−1)、59 Ni (0.60 ~ 1.0 Bq·g−1)、60 Co (0.74 ~ 70 Bq·g−1)、63 Ni (0.60 ~ 94 Bq·g−1)、90 Sr (0.25 ~ 5.0 Bq·g−1)、137 Cs (0.64 ~ 8.7 Bq·g−1)和152 Eu (0.19 ~ 2.9)
{"title":"Radiochemical Analysis of Filters Used During the Decommissioning of Research Reactors for Disposal","authors":"Kyungwon Suh, Jung Bo Yoo, K. Choi, Gi-Yong Kim, Si-duk Oh, Kanghyun Yoo, Kwang Eun Lee, S. Lee, Young Sang Lee, Hyeju Lee, Junhyuck Kim, K. Jung, Sora Choi, T. Park","doi":"10.7733/jnfcwt.2022.035","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.035","url":null,"abstract":"The decommissioning of nuclear facilities produces various types of radiologically contaminated waste. In addition, dismantlement activities, including cutting, packing, and clean-up at the facility site, result in secondary radioactive waste such as filters, resin, plastic, and clothing. Determining of the radionuclide content of this waste is an important step for the determination of a suitable management strategy including classification and disposal. In this work, we radiochemically characterized the radionuclide activities of filters used during the decommissioning of Korea Research Reactors (KRRs) 1 and 2. The results indicate that the filter samples contained mainly 3 H (500–3,600 Bq·g −1 ), 14 C (7.5–29 Bq·g −1 ), 55 Fe (1.1– 7.1 Bq·g −1 ), 59 Ni (0.60–1.0 Bq·g −1 ), 60 Co (0.74–70 Bq·g −1 ), 63 Ni (0.60–94 Bq·g −1 ), 90 Sr (0.25–5.0 Bq·g −1 ), 137 Cs (0.64–8.7 Bq·g −1 ), and 152 Eu (0.19–2.9","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"72 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-12-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90801217","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}
{"title":"Repurposing a Spent Nuclear Fuel Cask for Disposal of Solid Intermediate Level Radioactive Waste From Decommissioning of a Nuclear Power Plant\u0000in Korea","authors":"Wonjune Mah, Chang-Lak Kim","doi":"10.7733/jnfcwt.2022.024","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.024","url":null,"abstract":",","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"1 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85854243","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}
Young Hwan Hwang, S. Kim, Mi-hyun Lee, S. Hong, Cheon-Woo Kim
Nuclear power plant decommissioning generates significant concrete waste, which is slightly contaminated, and expected to be classified as clearance concrete waste. Clearance concrete waste is generally crushed into rubble at the site or a satellite treatment facility for practical disposal purposes. During the process, workers are exposed to radiation from the nuclides in concrete waste. The treatment processes consist of concrete cutting/crushing, transportation, and loading/unloading. Work - ers’ radiation exposure during the process was systematically studied. A shielding package comprising a cylindrical and hexahedron structure was considered to reduce workers’ radiation exposure, and improved the treatment process’s efficiency. The shielding package’s effect on workers’ radiation exposure during the cutting and crushing process was also studied. The calculated annual radiation exposure of concrete treatment workers was below 1 mSv, which is the annual radiation exposure limit for members of the public. It was also found that workers involved in cutting and crushing were exposed the most.
{"title":"Safety Analysis of Concrete Treatment Workers in Decommissioning of Nuclear Power Plant","authors":"Young Hwan Hwang, S. Kim, Mi-hyun Lee, S. Hong, Cheon-Woo Kim","doi":"10.7733/jnfcwt.2022.027","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.027","url":null,"abstract":"Nuclear power plant decommissioning generates significant concrete waste, which is slightly contaminated, and expected to be classified as clearance concrete waste. Clearance concrete waste is generally crushed into rubble at the site or a satellite treatment facility for practical disposal purposes. During the process, workers are exposed to radiation from the nuclides in concrete waste. The treatment processes consist of concrete cutting/crushing, transportation, and loading/unloading. Work - ers’ radiation exposure during the process was systematically studied. A shielding package comprising a cylindrical and hexahedron structure was considered to reduce workers’ radiation exposure, and improved the treatment process’s efficiency. The shielding package’s effect on workers’ radiation exposure during the cutting and crushing process was also studied. The calculated annual radiation exposure of concrete treatment workers was below 1 mSv, which is the annual radiation exposure limit for members of the public. It was also found that workers involved in cutting and crushing were exposed the most.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"47 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82217798","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}
Allison Harward, Levi D. Gardner, Claire M. Decker Oldham, Krista Carlson, T. Yoo, G. Fredrickson, Michael N. Patterson, M. Simpson
{"title":"Water Sorption/Desorption Characteristics of Eutectic LiCl-KCl Salt-Occluded Zeolites","authors":"Allison Harward, Levi D. Gardner, Claire M. Decker Oldham, Krista Carlson, T. Yoo, G. Fredrickson, Michael N. Patterson, M. Simpson","doi":"10.7733/jnfcwt.2022.021","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.021","url":null,"abstract":"","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"47 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89822968","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}
Juneho Park, T. Kwon, Gyeol Han, Jin-Seop Kim, Chang-Ho Hong, Hang-Lo Lee
{"title":"Damage Monitoring of Concrete With Acoustic Emission Method for Nuclear Waste Storage: Effect of Temperature and Water Immersion","authors":"Juneho Park, T. Kwon, Gyeol Han, Jin-Seop Kim, Chang-Ho Hong, Hang-Lo Lee","doi":"10.7733/jnfcwt.2022.030","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.030","url":null,"abstract":"","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"97 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79220526","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}
{"title":"The Transport of Radionuclides Released From Nuclear Facilities and Nuclear Wastes in the Marine Environment at Oceanic Scales","authors":"R. Periáñez","doi":"10.7733/jnfcwt.2022.029","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.029","url":null,"abstract":"","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"109 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73224720","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}
The safety of a KTC-360 transport cask, a large-capacity pressurized heavy-water reactor transport cask that transports CANDU spent nuclear fuel discharged from the reactor after burning in a pressurized heavy-water reactor, must be demon-strated under the normal transport and accident conditions specified under transport cask regulations. To confirm the thermal integrity of this cask under normal transport and accident conditions, high-temperature and fire tests were performed using a one-third slice model of an actual KTC-360 cask. The results revealed that the surface temperature of the cask was 62°C, indicating that such casks must be transported separately. The highest temperature of the CANDU spent nuclear fuel was pre - dicted to be lower than the melting temperature of Zircaloy-4, which was the sheath material used. Therefore, if normal op - erating conditions are applied, the thermal integrity of a KTC-360 cask can be maintained under normal transport conditions. The fire test revealed that the maximum temperatures of the structural materials, stainless steel, and carbon steel were 446°C lower than the permitted maximum temperatures, proving the thermal integrity of the cask under fire accident conditions.
{"title":"Experimental Evaluation of the Thermal Integrity of a Large Capacity Pressurized Heavy Water Reactor Transport Cask","authors":"K. Bang, Yun-young Yang, W. Choi","doi":"10.7733/jnfcwt.2022.028","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.028","url":null,"abstract":"The safety of a KTC-360 transport cask, a large-capacity pressurized heavy-water reactor transport cask that transports CANDU spent nuclear fuel discharged from the reactor after burning in a pressurized heavy-water reactor, must be demon-strated under the normal transport and accident conditions specified under transport cask regulations. To confirm the thermal integrity of this cask under normal transport and accident conditions, high-temperature and fire tests were performed using a one-third slice model of an actual KTC-360 cask. The results revealed that the surface temperature of the cask was 62°C, indicating that such casks must be transported separately. The highest temperature of the CANDU spent nuclear fuel was pre - dicted to be lower than the melting temperature of Zircaloy-4, which was the sheath material used. Therefore, if normal op - erating conditions are applied, the thermal integrity of a KTC-360 cask can be maintained under normal transport conditions. The fire test revealed that the maximum temperatures of the structural materials, stainless steel, and carbon steel were 446°C lower than the permitted maximum temperatures, proving the thermal integrity of the cask under fire accident conditions.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"1 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79187321","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}
Callum Robinson, White Matthew, S. Shaw, K. Morris, J. Graham, J. Lloyd
60+ Years of nuclear power generation has led to a significant legacy of radioactively contaminated land at a number of nuclear licenced “mega sites” around the world. The safe management and remediation of these sites is key to ensuring there environmental stewardship in the long term. Bioremediation utilizes a variety of microbially mediated processes such as, enzymatically driven metal reduction or biominerialisation, to sequester radioactive contaminants from the subsurface limiting their migration through the geosphere. Additionally, some of these process can provide environmentally stable sinks for radioactive contaminants, through formation of highly insoluble mineral phases such as calcium phosphates and carbonates, which can incorporate a range of radionuclides into their structure. Bioremediation options have been consid - ered and deployed in preference to conventional remediation techniques at a number of nuclear “mega” sites. Here, we review the applications of bioremediation technologies at three key nuclear licenced sites; Rifle and Hanford, USA and Sellafield, UK, in the remediation of radioactively contaminated land.
{"title":"Bioremediation Options for Nuclear Sites a Review of an Emerging Technology","authors":"Callum Robinson, White Matthew, S. Shaw, K. Morris, J. Graham, J. Lloyd","doi":"10.7733/jnfcwt.2022.026","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.026","url":null,"abstract":"60+ Years of nuclear power generation has led to a significant legacy of radioactively contaminated land at a number of nuclear licenced “mega sites” around the world. The safe management and remediation of these sites is key to ensuring there environmental stewardship in the long term. Bioremediation utilizes a variety of microbially mediated processes such as, enzymatically driven metal reduction or biominerialisation, to sequester radioactive contaminants from the subsurface limiting their migration through the geosphere. Additionally, some of these process can provide environmentally stable sinks for radioactive contaminants, through formation of highly insoluble mineral phases such as calcium phosphates and carbonates, which can incorporate a range of radionuclides into their structure. Bioremediation options have been consid - ered and deployed in preference to conventional remediation techniques at a number of nuclear “mega” sites. Here, we review the applications of bioremediation technologies at three key nuclear licenced sites; Rifle and Hanford, USA and Sellafield, UK, in the remediation of radioactively contaminated land.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"17 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73041893","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}
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