China Institute for Radiation Protection had independently developed a multi-purpose radioactive waste pyrolysis incineration technology and built 3 incineration facilities in China, which were mainly used to treat solid waste and waste oil from nuclear facilities such as NPPs. The composition of solid waste included paper, cloth, plastic, rubber, etc. In order to solve the problems in the early operation of incineration facilities, targeted improvements had been made in the aspects of equipment anti-corrosion capability, secondary waste generation and system safety. The improved facilities had treated a large amount of low-level waste and operated for more than 15 years. The stability and reliability of the incineration system were verified, and the advancement of pyrolysis incineration technology was proved. Considering the current situation that the proportion of plastics in low-level waste is increasing, the process was optimized so that more plastics and resin can be incinerated. The optimized incineration system still showed good adaptability when the proportion of plastic in the waste composition over 60%. The research on miniaturization and mobile technology of incineration were continuously carried out for the small reactors or small nuclear facilities, so as to further improve the economy. Compared with the incineration facilities, the mobile incineration technology can reduce the floor space by more than 90% and cut the construction cost by more than 75% under the same capacity and meeting the emission requirements.
{"title":"Engineering Application and Research Progress of Low-Level Radioactive Waste Incineration Technology in China","authors":"Chu Haoran, Xu Wei, Zheng Bowen, Ru Jiasheng","doi":"10.1115/icone29-93364","DOIUrl":"https://doi.org/10.1115/icone29-93364","url":null,"abstract":"\u0000 China Institute for Radiation Protection had independently developed a multi-purpose radioactive waste pyrolysis incineration technology and built 3 incineration facilities in China, which were mainly used to treat solid waste and waste oil from nuclear facilities such as NPPs. The composition of solid waste included paper, cloth, plastic, rubber, etc. In order to solve the problems in the early operation of incineration facilities, targeted improvements had been made in the aspects of equipment anti-corrosion capability, secondary waste generation and system safety. The improved facilities had treated a large amount of low-level waste and operated for more than 15 years. The stability and reliability of the incineration system were verified, and the advancement of pyrolysis incineration technology was proved.\u0000 Considering the current situation that the proportion of plastics in low-level waste is increasing, the process was optimized so that more plastics and resin can be incinerated. The optimized incineration system still showed good adaptability when the proportion of plastic in the waste composition over 60%. The research on miniaturization and mobile technology of incineration were continuously carried out for the small reactors or small nuclear facilities, so as to further improve the economy. Compared with the incineration facilities, the mobile incineration technology can reduce the floor space by more than 90% and cut the construction cost by more than 75% under the same capacity and meeting the emission requirements.","PeriodicalId":249213,"journal":{"name":"Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management","volume":"22 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127832135","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}
Ye He, Dongsheng Zhou, Feng Liu, Xuefei Li, Xingdong Su, Jiawen Li, Jie Zhan
Polyvinyl alcohol (PVA), a high molecular polymer, has good barrier property, acid or alkali resistance and degradability, which could be used as personal radiation protective equipment and pollution control articles in the nuclear industry, resulting in degradable radioactive technical wastes after use. The degradation treatment process of PVA degradable technology waste can realize validity separation of radionuclides and reduce the output of radioactive solid waste. In this study, MnxOy/γ-Al2O3, CuxOy/γ-Al2O3, FexOy/γ-Al2O3 and FexCuyMnzOw/γ-Al2O3 nanoparticles were prepared by the impregnation-calcination method, which were used as catalysts for the oxidative degradation of ultra-high concentration PVA organic waste solution, and the effects of initial pH of polyvinyl alcohol (PVA) solution, hydrogen peroxide (H2O2) dosing, catalyst dosing and initial concentration of PVA solution on the degradation of PVA were analyzed. The results showed that the best overall degradability was achieved by using FexCuyMnzOw/γ-Al2O3 nanoparticles as catalysts with the initial reaction concentration of PVA at 1%, the initial pH of the solution at 3, the reaction temperature at 60 °C, the catalyst dosage at 0.5 g/L and the H2O2 dosage at 60 mL/L. At this time, the concentration decrease rate of PVA could reach more than 95 %, the viscosity average molecular weight of degradation products reached 1395, the molecular weight decrease rate reached 99 %, and the degradation products mainly included butanone, benzaldehyde, hexanal, acetic acid and other unsaturated small molecules. In addition, the mechanism of hydroxyl radical generation by nanoparticles catalyzing hydrogen peroxide was discussed, and the reaction pathway of oxidative degradation of PVA macromolecules by hydroxyl radicals was proposed, which provided a reference for volume reduction treatment of PVA degradable waste in nuclear industry.
{"title":"Study on the Influencing Factors of Oxidation Degradation for High Concentration Polyvinyl Alcohol Wastewater in Heterogeneous Fenton System","authors":"Ye He, Dongsheng Zhou, Feng Liu, Xuefei Li, Xingdong Su, Jiawen Li, Jie Zhan","doi":"10.1115/icone29-90445","DOIUrl":"https://doi.org/10.1115/icone29-90445","url":null,"abstract":"\u0000 Polyvinyl alcohol (PVA), a high molecular polymer, has good barrier property, acid or alkali resistance and degradability, which could be used as personal radiation protective equipment and pollution control articles in the nuclear industry, resulting in degradable radioactive technical wastes after use. The degradation treatment process of PVA degradable technology waste can realize validity separation of radionuclides and reduce the output of radioactive solid waste. In this study, MnxOy/γ-Al2O3, CuxOy/γ-Al2O3, FexOy/γ-Al2O3 and FexCuyMnzOw/γ-Al2O3 nanoparticles were prepared by the impregnation-calcination method, which were used as catalysts for the oxidative degradation of ultra-high concentration PVA organic waste solution, and the effects of initial pH of polyvinyl alcohol (PVA) solution, hydrogen peroxide (H2O2) dosing, catalyst dosing and initial concentration of PVA solution on the degradation of PVA were analyzed. The results showed that the best overall degradability was achieved by using FexCuyMnzOw/γ-Al2O3 nanoparticles as catalysts with the initial reaction concentration of PVA at 1%, the initial pH of the solution at 3, the reaction temperature at 60 °C, the catalyst dosage at 0.5 g/L and the H2O2 dosage at 60 mL/L. At this time, the concentration decrease rate of PVA could reach more than 95 %, the viscosity average molecular weight of degradation products reached 1395, the molecular weight decrease rate reached 99 %, and the degradation products mainly included butanone, benzaldehyde, hexanal, acetic acid and other unsaturated small molecules. In addition, the mechanism of hydroxyl radical generation by nanoparticles catalyzing hydrogen peroxide was discussed, and the reaction pathway of oxidative degradation of PVA macromolecules by hydroxyl radicals was proposed, which provided a reference for volume reduction treatment of PVA degradable waste in nuclear industry.","PeriodicalId":249213,"journal":{"name":"Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management","volume":"15 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130520534","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}
Hui Liang, Erkan Nejdet, Kai Wang, A. Sharma, Shunichi Suzuki
In the future decommissioning plan of the damaged Fukushima Daiichi nuclear reactors, the melted and re-solidified fuel debris at the bottom of the reactor pressure vessel and primary containment vessel will be cut into small pieces before retrieving them from reactor buildings. Submicron aerosol particles that generated during cutting operations must be removed inside the containment vessel before they escape to the environment. The existed spray system inside the containment vessel can be used to remove these aerosol particles under different collection mechanisms. In this study, a new numerical model is developed to simulate both the aerosol generation by cutting fuel debris and aerosol removal by spray injection in the open-source CFD code OpenFOAM using the geometry of our model facility (UTARTS facility). Simulation results provide detailed information about the time evolution of aerosol distribution, and also show that aerosol generation rate has no influence on aerosol removal efficiency, and larger particles can be removed faster because of stronger inertial impaction. The newly developed numerical model with considering both aerosol generation due to cut fuel debris and aerosol scavenging by spray droplets can be used in the real-size containment vessel of Fukushima Daiichi nuclear reactors to optimize the design of future spray systems.
{"title":"Numerical Simulation of Aerosol Generation and Aerosol Spray Scavenging During Fukushima Daiichi Decommissioning","authors":"Hui Liang, Erkan Nejdet, Kai Wang, A. Sharma, Shunichi Suzuki","doi":"10.1115/icone29-89098","DOIUrl":"https://doi.org/10.1115/icone29-89098","url":null,"abstract":"\u0000 In the future decommissioning plan of the damaged Fukushima Daiichi nuclear reactors, the melted and re-solidified fuel debris at the bottom of the reactor pressure vessel and primary containment vessel will be cut into small pieces before retrieving them from reactor buildings. Submicron aerosol particles that generated during cutting operations must be removed inside the containment vessel before they escape to the environment. The existed spray system inside the containment vessel can be used to remove these aerosol particles under different collection mechanisms. In this study, a new numerical model is developed to simulate both the aerosol generation by cutting fuel debris and aerosol removal by spray injection in the open-source CFD code OpenFOAM using the geometry of our model facility (UTARTS facility). Simulation results provide detailed information about the time evolution of aerosol distribution, and also show that aerosol generation rate has no influence on aerosol removal efficiency, and larger particles can be removed faster because of stronger inertial impaction. The newly developed numerical model with considering both aerosol generation due to cut fuel debris and aerosol scavenging by spray droplets can be used in the real-size containment vessel of Fukushima Daiichi nuclear reactors to optimize the design of future spray systems.","PeriodicalId":249213,"journal":{"name":"Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116574721","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}
Fission ionization chamber of Nuclear Instrumentation System (NIS) is an essential equipment for the nuclear power plant. By measuring the neutron fluence rate in the immediate range (IR), the power level of the reactor can be determined. In order to ensure its performance to get accurate measurement results, the reliability and aging degree should be analyzed so that we can replace the fission ionization chamber before it expires. In this paper, the aging mechanism of NIS fission ionization chamber is analyzed and calculated from four aspects: moderator degradation, irradiation damage, sensitive uranium plating loss and detector working gas loss. The calculation model is the fission ionization chamber developed by our institute. As the results indicated, moderator degradation and irradiation damage of neutrons cause tiny effect of detector performance. The uranium plating loss caused by neutron reaction leads to 2% detector sensitivity decrease when irradiation time reaches 45.8 years. The working gas loss leads to less than 2% detector sensitivity decrease in 146.4 years if the gas leakage is highly controlled. Furthermore, the mean time between failure (MTBF) is analyzed and calculated. This research provides detailed analysis and methods to determine the reliability and life of NIS fission ionization chamber. And the results indicated that the detector developed by our institute has high reliability to apply in the cruel environment outside the reactor.
{"title":"Analysis of Reliability and Life of Fission Ionization Chamber of Nuclear Instrumentation System (NIS)","authors":"Yulin Zhou, Shunli Qiu, Mengtuan Ge, Guangzhi Sun, Wei Xiao, Haifeng Liu","doi":"10.1115/icone29-92683","DOIUrl":"https://doi.org/10.1115/icone29-92683","url":null,"abstract":"\u0000 Fission ionization chamber of Nuclear Instrumentation System (NIS) is an essential equipment for the nuclear power plant. By measuring the neutron fluence rate in the immediate range (IR), the power level of the reactor can be determined. In order to ensure its performance to get accurate measurement results, the reliability and aging degree should be analyzed so that we can replace the fission ionization chamber before it expires. In this paper, the aging mechanism of NIS fission ionization chamber is analyzed and calculated from four aspects: moderator degradation, irradiation damage, sensitive uranium plating loss and detector working gas loss. The calculation model is the fission ionization chamber developed by our institute. As the results indicated, moderator degradation and irradiation damage of neutrons cause tiny effect of detector performance. The uranium plating loss caused by neutron reaction leads to 2% detector sensitivity decrease when irradiation time reaches 45.8 years. The working gas loss leads to less than 2% detector sensitivity decrease in 146.4 years if the gas leakage is highly controlled. Furthermore, the mean time between failure (MTBF) is analyzed and calculated. This research provides detailed analysis and methods to determine the reliability and life of NIS fission ionization chamber. And the results indicated that the detector developed by our institute has high reliability to apply in the cruel environment outside the reactor.","PeriodicalId":249213,"journal":{"name":"Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129623963","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}
Minzhi Ruan, Yingzi Liu, Jinyao Zhang, Minhang Sun, Xuelian Liu
Prior to radioactive operations, the Vitrification Plant of China (VPC) will implement a cold-commissioning plan or strategy that will include functional test, water test, simulant test and glass pouring test to not only test the process systems, auxiliary systems and melter performance, but also allow operators to increase facility operating experience and be familiar with remote handling in hot cells before introducing radioactive material into the plant. The process technique used is based on the German liquid fed ceramic-lined electric waste glass melter (LFCM) designed to process high level liquid waste (HLLW) containing highly noble metals (Ru, Rh, Pd). Several batches of simulants tests are performed and the operation data including melter temperature and initiating procedure are analyzed. A maximum process rate is determined according to the applied process parameters including the high operating temperature. And in different operating modes, including idling mode and operating mode, the effect of different feed rates on the formation of the cold cap and the temperature in different areas of the melter are investigated. The paper gives an overview about the current status of the VPC plant. The strategy of commissioning and cold test operations are described in detail.
{"title":"Commissioning and Cold Test of HLLW Vitrification Plant of China","authors":"Minzhi Ruan, Yingzi Liu, Jinyao Zhang, Minhang Sun, Xuelian Liu","doi":"10.1115/icone29-93047","DOIUrl":"https://doi.org/10.1115/icone29-93047","url":null,"abstract":"\u0000 Prior to radioactive operations, the Vitrification Plant of China (VPC) will implement a cold-commissioning plan or strategy that will include functional test, water test, simulant test and glass pouring test to not only test the process systems, auxiliary systems and melter performance, but also allow operators to increase facility operating experience and be familiar with remote handling in hot cells before introducing radioactive material into the plant. The process technique used is based on the German liquid fed ceramic-lined electric waste glass melter (LFCM) designed to process high level liquid waste (HLLW) containing highly noble metals (Ru, Rh, Pd).\u0000 Several batches of simulants tests are performed and the operation data including melter temperature and initiating procedure are analyzed. A maximum process rate is determined according to the applied process parameters including the high operating temperature. And in different operating modes, including idling mode and operating mode, the effect of different feed rates on the formation of the cold cap and the temperature in different areas of the melter are investigated.\u0000 The paper gives an overview about the current status of the VPC plant. The strategy of commissioning and cold test operations are described in detail.","PeriodicalId":249213,"journal":{"name":"Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management","volume":"7 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129193769","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}
During the nuclear fuel cycle, a large amount of radioactive cesium is produced, and at the same time, it is difficult to safely dispose of because of its extremely soluble in water and low boiling point. The safe disposal of radioactive cesium is a problem that needs to be solved urgently. The currently used methods to treat cesium-containing wastewater such as cement fixation, glass solidification and ion exchange, have certain drawbacks, and urgently need to be further optimized. Pollucite is an analcite molecular sieve. Many studies have shown that it is one of the potential final choices for radioactive cesium. Pollucite has an appropriate pore size, without destroying the structure of pollucite, radioactive cesium cannot diffuse out of pore of pollucite, pollucite also has a good stability and high cesium loading rate. In previous studies, pollucite needs to be synthesized under high temperature conditions above 1000°C. This method will cause the volatilization of cesium and increase the difficulty of exhaust gas treatment. How to quickly synthesize pollucite at a lower temperature has become an important research direction for the safe disposal of caesium. Different from the traditional calcination method to synthesize pollucite, this paper uses hydrothermal method to simulate the generation environment of zeolite in nature, and realizes the synthesis of pollucite at a lower temperature. Using cesium contained in simulated wastewater as synthetic raw materials, combined with commonly used silicon sources and aluminum sources as synthetic raw material, through exploring different reaction conditions such as reaction temperature, reaction time, and alkali addition, the hydrothermal synthesis of pollucite was finally successfully realized. Then the influence of different reaction conditions on synthesis and cesium removal efficiency was investigated, and its growth mechanism was also analyzed. Finally, it was realized that pollucite was successfully synthesized under 150°C hydrothermal conditions using common chemical reagents as raw materials, which further promoted pollucite application in the safe disposal of radioactive cesium.
{"title":"High Efficient Mineralization of Cesium in Waste Liquid by Hydrothermal Method","authors":"K. Gao, Wendong Feng, Xiaojun Yan, Xiaobin Guo, Xiao-Hua Cui, Xiliang Guo","doi":"10.1115/icone29-90716","DOIUrl":"https://doi.org/10.1115/icone29-90716","url":null,"abstract":"\u0000 During the nuclear fuel cycle, a large amount of radioactive cesium is produced, and at the same time, it is difficult to safely dispose of because of its extremely soluble in water and low boiling point. The safe disposal of radioactive cesium is a problem that needs to be solved urgently. The currently used methods to treat cesium-containing wastewater such as cement fixation, glass solidification and ion exchange, have certain drawbacks, and urgently need to be further optimized. Pollucite is an analcite molecular sieve. Many studies have shown that it is one of the potential final choices for radioactive cesium. Pollucite has an appropriate pore size, without destroying the structure of pollucite, radioactive cesium cannot diffuse out of pore of pollucite, pollucite also has a good stability and high cesium loading rate. In previous studies, pollucite needs to be synthesized under high temperature conditions above 1000°C. This method will cause the volatilization of cesium and increase the difficulty of exhaust gas treatment. How to quickly synthesize pollucite at a lower temperature has become an important research direction for the safe disposal of caesium. Different from the traditional calcination method to synthesize pollucite, this paper uses hydrothermal method to simulate the generation environment of zeolite in nature, and realizes the synthesis of pollucite at a lower temperature. Using cesium contained in simulated wastewater as synthetic raw materials, combined with commonly used silicon sources and aluminum sources as synthetic raw material, through exploring different reaction conditions such as reaction temperature, reaction time, and alkali addition, the hydrothermal synthesis of pollucite was finally successfully realized. Then the influence of different reaction conditions on synthesis and cesium removal efficiency was investigated, and its growth mechanism was also analyzed. Finally, it was realized that pollucite was successfully synthesized under 150°C hydrothermal conditions using common chemical reagents as raw materials, which further promoted pollucite application in the safe disposal of radioactive cesium.","PeriodicalId":249213,"journal":{"name":"Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management","volume":"84 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132564227","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}
Xin Li, Yongguo Li, Jie Yu, Xin Chen, Jianrong Hou, Jian Li, Dangui Qiu, Xu Shi
As the most important impregnation component of iodine adsorption materials, Triethylenediamine (TEDA) has a disadvantage of being volatile. This disadvantage has a negative impact on the adsorption performance of iodine adsorber, resulting in an increase in the operation cost of nuclear facilities and the amount of solid waste. Based on this problem, TEDA ionic liquids (TEDAILs) was prepared by quaternization of TEDA, which is a method to effectively solve the volatile problem of TEDA. The changes of the yield of TEDAILs and the proportion of single-cationic ionic liquids (SCILs) were investigated under different reactant ratio, reaction temperature and reaction time. According to the law of change, the optimal preparation condition of TEDAILs was revealed. In addition, the composition of the TEDAILs was analyzed by infrared spectrum and nuclear magnetic spectrum, and the thermal stability was also verified by thermogravimetric analysis. On this basis, TEDAILs loaded activated carbon fibers (TEDAILs-ACF) was designed and prepared, and the iodine adsorption performance was tested. Verification test results show that the complete decomposition temperature of TEDAILs is about 362 °C, which is about 187% higher than that of TEDA. Moreover, the adsorption efficiency of radioactive methyl iodine by TEDAILs-ACF under normal temperature and humidity is 99.94%. In summary, TEDAILs-ACF as radioactive methyl-iodine adsorption material has potential application prospect.
{"title":"Study on Preparation and Radioactive Methyl-Iodine Adsorption Performance of TEDA Ionic Liquids","authors":"Xin Li, Yongguo Li, Jie Yu, Xin Chen, Jianrong Hou, Jian Li, Dangui Qiu, Xu Shi","doi":"10.1115/icone29-90275","DOIUrl":"https://doi.org/10.1115/icone29-90275","url":null,"abstract":"\u0000 As the most important impregnation component of iodine adsorption materials, Triethylenediamine (TEDA) has a disadvantage of being volatile. This disadvantage has a negative impact on the adsorption performance of iodine adsorber, resulting in an increase in the operation cost of nuclear facilities and the amount of solid waste. Based on this problem, TEDA ionic liquids (TEDAILs) was prepared by quaternization of TEDA, which is a method to effectively solve the volatile problem of TEDA. The changes of the yield of TEDAILs and the proportion of single-cationic ionic liquids (SCILs) were investigated under different reactant ratio, reaction temperature and reaction time. According to the law of change, the optimal preparation condition of TEDAILs was revealed. In addition, the composition of the TEDAILs was analyzed by infrared spectrum and nuclear magnetic spectrum, and the thermal stability was also verified by thermogravimetric analysis. On this basis, TEDAILs loaded activated carbon fibers (TEDAILs-ACF) was designed and prepared, and the iodine adsorption performance was tested. Verification test results show that the complete decomposition temperature of TEDAILs is about 362 °C, which is about 187% higher than that of TEDA. Moreover, the adsorption efficiency of radioactive methyl iodine by TEDAILs-ACF under normal temperature and humidity is 99.94%. In summary, TEDAILs-ACF as radioactive methyl-iodine adsorption material has potential application prospect.","PeriodicalId":249213,"journal":{"name":"Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management","volume":"10 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116883881","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}
Most of the radioactive waste generated during the decommissioning of nuclear power plants are relatively low in radioactivity, except for the reactor pressure vessel, reactor internals and primary shielding walls, which have high levels of radioactivity. However, the treatment and disposal costs of decommissioning waste account for a high proportion of the total decommissioning cost. In order to minimize the decommissioning waste and to plan the decommissioning costs, it is necessary to study and estimate the total quantity of decommissioning radioactive waste in the design phase. This paper presents the statistical method for estimation of decommissioning radioactive waste quantity, gives the complete steps for estimating decommissioning radioactive waste quantity, and determines the waste quantity estimation principle for each type of decommissioning radioactive waste. Finally, the estimation task based on a Chinese typical million kilowatt nuclear power station single unit is reasonably completed. It is estimated that the quantity of decommissioning radioactive waste generated by this nuclear power station single unit is about 12000m3, which is similar to that of the same type-unit in the world. This proves the rationality of the method for estimating decommissioning radioactive waste quantity proposed in this paper.
{"title":"Estimation of Decommissioning Radioactive Wastes Quantity for Nuclear Power Plant","authors":"Senquan Li","doi":"10.1115/icone29-91672","DOIUrl":"https://doi.org/10.1115/icone29-91672","url":null,"abstract":"\u0000 Most of the radioactive waste generated during the decommissioning of nuclear power plants are relatively low in radioactivity, except for the reactor pressure vessel, reactor internals and primary shielding walls, which have high levels of radioactivity. However, the treatment and disposal costs of decommissioning waste account for a high proportion of the total decommissioning cost. In order to minimize the decommissioning waste and to plan the decommissioning costs, it is necessary to study and estimate the total quantity of decommissioning radioactive waste in the design phase. This paper presents the statistical method for estimation of decommissioning radioactive waste quantity, gives the complete steps for estimating decommissioning radioactive waste quantity, and determines the waste quantity estimation principle for each type of decommissioning radioactive waste. Finally, the estimation task based on a Chinese typical million kilowatt nuclear power station single unit is reasonably completed. It is estimated that the quantity of decommissioning radioactive waste generated by this nuclear power station single unit is about 12000m3, which is similar to that of the same type-unit in the world. This proves the rationality of the method for estimating decommissioning radioactive waste quantity proposed in this paper.","PeriodicalId":249213,"journal":{"name":"Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management","volume":"918 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116180915","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}
Dezhong Wang, Hui Yang, W. Gu, Jie Qiu, Wentao Zhou
Segmented gamma scanning (SGS) and tomographic gamma scanning (TGS) are two traditional detection techniques for low and intermediate level radioactive waste drum. However, detection accuracy of SGS is low and detection time of TGS is very long. This paper summaries three types of new gamma scanning techniques to assay the radioactive waste drum. Compared with SGS and TGS, these techniques exhibit the well-balanced performance which can improve the detection accuracy and shorten the detection time.
{"title":"New Gamma Scanning Technology for 200L and 400L Low and Intermediate Level Solid Waste","authors":"Dezhong Wang, Hui Yang, W. Gu, Jie Qiu, Wentao Zhou","doi":"10.1115/icone29-92372","DOIUrl":"https://doi.org/10.1115/icone29-92372","url":null,"abstract":"\u0000 Segmented gamma scanning (SGS) and tomographic gamma scanning (TGS) are two traditional detection techniques for low and intermediate level radioactive waste drum. However, detection accuracy of SGS is low and detection time of TGS is very long. This paper summaries three types of new gamma scanning techniques to assay the radioactive waste drum. Compared with SGS and TGS, these techniques exhibit the well-balanced performance which can improve the detection accuracy and shorten the detection time.","PeriodicalId":249213,"journal":{"name":"Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management","volume":"2 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126111000","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}
Decommissioning for nuclear power plant is complex project, which is needed to be taken into account during the early phase of design stage. Many researches and practices have already done for nuclear decommissioning activities. The decommissioning chapter is defined in preliminary safety analysis report for new build nuclear project, which needs to describe the design and management activities. According to the preliminary research for decommissioning requirement and scheme, many activities are direct related to layout design of nuclear buildings. In this paper, the decommissioning factors for layout design of nuclear buildings are summarized, which can be used as reference and supply some practices for other project.
{"title":"Decommissioning Considerations for Layout Design of Nuclear Buildings","authors":"W. He, Weiyang Jiang","doi":"10.1115/icone29-89610","DOIUrl":"https://doi.org/10.1115/icone29-89610","url":null,"abstract":"\u0000 Decommissioning for nuclear power plant is complex project, which is needed to be taken into account during the early phase of design stage. Many researches and practices have already done for nuclear decommissioning activities. The decommissioning chapter is defined in preliminary safety analysis report for new build nuclear project, which needs to describe the design and management activities. According to the preliminary research for decommissioning requirement and scheme, many activities are direct related to layout design of nuclear buildings. In this paper, the decommissioning factors for layout design of nuclear buildings are summarized, which can be used as reference and supply some practices for other project.","PeriodicalId":249213,"journal":{"name":"Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128499765","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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