Pub Date : 2018-03-31DOI: 10.7733/JNFCWT.2018.16.1.65
N. Kamaruzaman, D. Kessel, Chang-Lak Kim
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{"title":"Management of Spent Ion-Exchange Resins From Nuclear Power Plant by Blending Method","authors":"N. Kamaruzaman, D. Kessel, Chang-Lak Kim","doi":"10.7733/JNFCWT.2018.16.1.65","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.65","url":null,"abstract":",","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"24 1","pages":"65-82"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88801426","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}
Pub Date : 2018-03-31DOI: 10.7733/JNFCWT.2018.16.1.49
Eil-Hee Lee, Jimin Kim, Hyung‐Ju Kim, I. Kim, D. Chung, Kwang-Wook Kim, Keunyoung Lee, B. Seo
For the immobilization of high-radioactive nuclides such as Cs and Sr by high-temperature thermal decomposition, this study was carried out to investigate the phase transformation with calcined temperature by using TGA (thermogravimetric analysis) and XRD (X-ray diffraction) in the Cs-adsorbed CHA (chabazite zeolite of K type)-Cs and CHA-PCFC (potassium cobalt ferrocyanide)-Cs zeolite system, and Sr-adsorbed 4A-Sr and BaA-Sr zeolite system, respectively. In the case of CHA-Cs zeolite system, the structure of CHA-Cs remained at up to 900°C and recrystallized to pollucite (CsAlSi2O6) at 1,100°C after undergoing amorphous phase at 1,000°C. However, the CHA-CFC-Cs zeolite system retained the CHA-PCFC-Cs structure up to 700°C, but its structure collapsed in 900~1,000°C, and then transformed to amorphous phase, and recrystallized to pollucite at 1,100°C. In the case of 4A-Sr zeolite system, on the other hand, the structure of 4A-Sr maintained up to 700°C and its phase transformed to amorphous at 800°C, and recrystallized to Sr-feldspar (SrAl2Si2O8, hexagonal) at 900°C and to SrAl2Si2O8 (triclinic) at 1,100°C. However, the BaA-Sr zeolite system structure began to break down at below 500°C, and then transformed to amorphous phase in 500~900°C and recrystallized to Ba/Sr-feldspar (coexistence of Ba0.9Sr0.1Al2Si2O8 and Ba0.5Sr0.5Al2Si2O8) at 1,100°C. All of the above zeolite systems recrystallized to mineral phase through the dehydration/(decomposition)→ amorphous → recrystallization with increasing temperature. Although further study of the volatility and leachability of Cs and Sr in the high-temperature thermal decomposition process is required, Cs and Sr adsorbed in each zeolite system are mineralized as pollucite, Sr-feldspar and Ba/Sr-feldspar. Therefore, Cs and Sr seen to be able to completely immobilize in the calcining wasteform/(solidified wasteform).
为了利用高温热分解固定高放射性核素Cs和Sr，本研究分别利用热重分析(TGA)和x射线衍射(XRD)研究了Cs吸附CHA (K型辉石沸石)-Cs和CHA- pcfc(钴亚铁氰化钾)-Cs沸石体系和Sr吸附4A-Sr和BaA-Sr沸石体系在煅烧温度下的相变。在CHA-Cs沸石体系中，在高达900℃时，CHA-Cs的结构保持不变，在1000℃时经过非晶相，在1100℃时再结晶为污染石(CsAlSi2O6)。而CHA-CFC-Cs分子筛体系在700℃时仍保持CHA-PCFC-Cs的结构，但在900~ 1000℃时结构崩溃，然后转变为非晶相，在1100℃时再结晶为污染石。而4A-Sr沸石体系在700℃时结构保持不变，800℃时相变为无定形，900℃时再结晶为sr长石(SrAl2Si2O8，六角形)，1100℃时再结晶为SrAl2Si2O8(三斜形)。而BaA-Sr沸石体系结构在500℃以下开始分解，500~900℃转变为非晶相，1100℃重结晶为Ba/ sr -长石(Ba0.9Sr0.1Al2Si2O8和Ba0.5Sr0.5Al2Si2O8共存)。随着温度的升高，上述沸石体系均经过脱水/(分解)→无定形→再结晶的过程再结晶为矿物相。虽然需要进一步研究Cs和Sr在高温热分解过程中的挥发性和浸出性，但在每个沸石体系中吸附的Cs和Sr都被矿化为污染石、Sr-长石和Ba/Sr-长石。因此，Cs和Sr似乎能够完全固定在煅烧废物/(固化废物)中。
{"title":"High-temperature Thermal Decomposition of Cs-adsorbed CHA-Cs and CHA-PCFC-Cs Zeolite System, and Sr-adsorbed 4A-Sr and BaA-Sr Zeolite System","authors":"Eil-Hee Lee, Jimin Kim, Hyung‐Ju Kim, I. Kim, D. Chung, Kwang-Wook Kim, Keunyoung Lee, B. Seo","doi":"10.7733/JNFCWT.2018.16.1.49","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.49","url":null,"abstract":"For the immobilization of high-radioactive nuclides such as Cs and Sr by high-temperature thermal decomposition, this study was carried out to investigate the phase transformation with calcined temperature by using TGA (thermogravimetric analysis) and XRD (X-ray diffraction) in the Cs-adsorbed CHA (chabazite zeolite of K type)-Cs and CHA-PCFC (potassium cobalt ferrocyanide)-Cs zeolite system, and Sr-adsorbed 4A-Sr and BaA-Sr zeolite system, respectively. In the case of CHA-Cs zeolite system, the structure of CHA-Cs remained at up to 900°C and recrystallized to pollucite (CsAlSi2O6) at 1,100°C after undergoing amorphous phase at 1,000°C. However, the CHA-CFC-Cs zeolite system retained the CHA-PCFC-Cs structure up to 700°C, but its structure collapsed in 900~1,000°C, and then transformed to amorphous phase, and recrystallized to pollucite at 1,100°C. In the case of 4A-Sr zeolite system, on the other hand, the structure of 4A-Sr maintained up to 700°C and its phase transformed to amorphous at 800°C, and recrystallized to Sr-feldspar (SrAl2Si2O8, hexagonal) at 900°C and to SrAl2Si2O8 (triclinic) at 1,100°C. However, the BaA-Sr zeolite system structure began to break down at below 500°C, and then transformed to amorphous phase in 500~900°C and recrystallized to Ba/Sr-feldspar (coexistence of Ba0.9Sr0.1Al2Si2O8 and Ba0.5Sr0.5Al2Si2O8) at 1,100°C. All of the above zeolite systems recrystallized to mineral phase through the dehydration/(decomposition)→ amorphous → recrystallization with increasing temperature. Although further study of the volatility and leachability of Cs and Sr in the high-temperature thermal decomposition process is required, Cs and Sr adsorbed in each zeolite system are mineralized as pollucite, Sr-feldspar and Ba/Sr-feldspar. Therefore, Cs and Sr seen to be able to completely immobilize in the calcining wasteform/(solidified wasteform).","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"85 1","pages":"49-58"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89033250","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}
Pub Date : 2018-03-31DOI: 10.7733/JNFCWT.2018.16.1.1
M. Simpson, Prashant Bagri
{"title":"Basis for a Minimalistic Salt Treatment Approach for Pyroprocessing Commercial Nuclear Fuel","authors":"M. Simpson, Prashant Bagri","doi":"10.7733/JNFCWT.2018.16.1.1","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.1","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"50 1","pages":"1-10"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79208812","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}
Pub Date : 2018-03-31DOI: 10.7733/jnfcwt.2018.16.1.123
Jin-Seop Kim, Seok Yoon, W. Cho, Y. Choi, Geon-Young Kim
{"title":"A Study on the Manufacturing Characteristics and Field Applicability of Engineering-scale Bentonite Buffer Block in a High-level Nuclear Waste Repository","authors":"Jin-Seop Kim, Seok Yoon, W. Cho, Y. Choi, Geon-Young Kim","doi":"10.7733/jnfcwt.2018.16.1.123","DOIUrl":"https://doi.org/10.7733/jnfcwt.2018.16.1.123","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"1 1","pages":"123-136"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74072171","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}
Pub Date : 2018-03-31DOI: 10.7733/JNFCWT.2018.16.1.11
X. Hou
{"title":"Tritium and 14 C in the Environment and Nuclear Facilities: Sources and Analytical Methods","authors":"X. Hou","doi":"10.7733/JNFCWT.2018.16.1.11","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.11","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"102 1","pages":"11-39"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86899677","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}
Pub Date : 2018-03-31DOI: 10.7733/JNFCWT.2018.16.1.107
Sang‐Ho Lee, Hyung-Woo Seo, Chang-Lak Kim
{"title":"Preparation of Radiological Environmental Impact Assessment for the Decommissioning of Nuclear Power Plant in Korea","authors":"Sang‐Ho Lee, Hyung-Woo Seo, Chang-Lak Kim","doi":"10.7733/JNFCWT.2018.16.1.107","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.107","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"20 1","pages":"107-122"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87165742","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}
Pub Date : 2018-03-31DOI: 10.7733/JNFCWT.2018.16.1.93
Keunyoung Lee, Maengkyo Oh, Jimin Kim, Eil-Hee Lee, Kim，Ik Soo, Kwang-Wook Kim, D. Chung, B. Seo
향후 원자력시설 해체 시 막대한 양의 해체 콘크리트 폐기물이 발생할 수 있음을 감안하였을 때, 방사성 콘크리트 폐기물의 최적 처리기술에 대한 면밀한 검토와 향후 기술개발 방향에 대한 논의는 반드시 필요하다. 본 논문에서는 방사성 콘크리트 폐기물의 국내외 발생 사례를 종합해 보고, 처리 대상이 되는 방사성 콘크...
{"title":"Trends in Technology Development for the Treatment of Radioactive Concrete Waste","authors":"Keunyoung Lee, Maengkyo Oh, Jimin Kim, Eil-Hee Lee, Kim，Ik Soo, Kwang-Wook Kim, D. Chung, B. Seo","doi":"10.7733/JNFCWT.2018.16.1.93","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.93","url":null,"abstract":"향후 원자력시설 해체 시 막대한 양의 해체 콘크리트 폐기물이 발생할 수 있음을 감안하였을 때, 방사성 콘크리트 폐기물의 최적 처리기술에 대한 면밀한 검토와 향후 기술개발 방향에 대한 논의는 반드시 필요하다. 본 논문에서는 방사성 콘크리트 폐기물의 국내외 발생 사례를 종합해 보고, 처리 대상이 되는 방사성 콘크...","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"1 1","pages":"93-105"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76725106","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}
Pub Date : 2018-03-31DOI: 10.7733/jnfcwt.2018.16.1.83
D. Koo, Hyun-Hee Sung, Sangbum Hong, B. Seo
{"title":"Characteristics of Solidified Cement of Electrokinetically Decontaminated Soil and Concrete Waste","authors":"D. Koo, Hyun-Hee Sung, Sangbum Hong, B. Seo","doi":"10.7733/jnfcwt.2018.16.1.83","DOIUrl":"https://doi.org/10.7733/jnfcwt.2018.16.1.83","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"79 1","pages":"83-91"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88909012","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}
Pub Date : 2018-03-31DOI: 10.7733/JNFCWT.2018.16.1.59
Tackjin Kim, D. Ahn, H. Eun, Sung-Jai Lee
{"title":"A Basic Study on Separation of U and Nd From LiCl-KCl-UCl 3 -NdCl 3 System","authors":"Tackjin Kim, D. Ahn, H. Eun, Sung-Jai Lee","doi":"10.7733/JNFCWT.2018.16.1.59","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.59","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"81 1","pages":"59-64"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76355803","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}
Pub Date : 2017-12-15DOI: 10.7733/JNFCWT.2017.15.4.369
김민성, 홍성욱, 박진백
In order to manage the uncertainty about the evaluation and analysis of the human intrusion scenario of the Gyeongju Low and Intermediate Level Radioactive Waste(LILW) disposal facility, the calculation result by the GENII code was assessed using the RESRAD code, which was developed to evaluate the radiation effects of contaminated soil. The post-drilling scenario was selected as a human intrusion scenario into the near-surface disposal facility to analyze the uncertainty of the modeling by identifying any limitations in the simulation of each code and comparing the evaluation results under the same input data conditions. The results revealed a difference in the migration of some nuclides between the codes, but confirmed that the dose trends at the end of the post-closure control period were similar for all exposure pathways. Based on the results of the dose evaluation predicted by RESRAD, sensitivity analysis on the input factors was performed and major input factors were derived. The uncertainty of the modeling results and the input factors were analyzed and the reliability of the safety evaluation results was confirmed. The results of this study can be applied to the implementation ‘Safety Case Program’ for the Gyeongju LILW disposal facility.
{"title":"Uncertainty Management on Human Intrusion Scenario Assessment of the Near Surface Disposal Facility for Low and Intermediate-Level Radioactive Waste: Comparative Analysis of RESRAD and GENII","authors":"김민성, 홍성욱, 박진백","doi":"10.7733/JNFCWT.2017.15.4.369","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.4.369","url":null,"abstract":"In order to manage the uncertainty about the evaluation and analysis of the human intrusion scenario of the Gyeongju Low and Intermediate Level Radioactive Waste(LILW) disposal facility, the calculation result by the GENII code was assessed using the RESRAD code, which was developed to evaluate the radiation effects of contaminated soil. The post-drilling scenario was selected as a human intrusion scenario into the near-surface disposal facility to analyze the uncertainty of the modeling by identifying any limitations in the simulation of each code and comparing the evaluation results under the same input data conditions. The results revealed a difference in the migration of some nuclides between the codes, but confirmed that the dose trends at the end of the post-closure control period were similar for all exposure pathways. Based on the results of the dose evaluation predicted by RESRAD, sensitivity analysis on the input factors was performed and major input factors were derived. The uncertainty of the modeling results and the input factors were analyzed and the reliability of the safety evaluation results was confirmed. The results of this study can be applied to the implementation ‘Safety Case Program’ for the Gyeongju LILW disposal facility.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"212 1","pages":"369-380"},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76266222","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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