Haoxiang Li, Weizhen Zheng, B. Du, Huaqiang Yin, Zhihao Hong, Long Wang, Xuedong He, Tengyu Ma, Xingtuan Yang
In high temperature gas cooled reactor (HTGR), there is a small amount of helium in the primary coolant (ppm level) impure impurities, which will corrode the alloy materials of high temperature reactor and affect the performance of equipment in high temperature environment. The coating preparation technology on the alloy surface can effectively protect the alloy matrix, greatly reduce the corrosion rate of alloy, and improve the reliability and safety of equipment. In this paper, a Cr2O3/α-Al2O3 multilayer barrier coating prepared by RF magnetron sputtering was used to coat Incoloy 800H alloy, and the corrosion behavior of Incoloy 800H alloy with and without coating under selected high-temperature impure helium was investigated. After the experiment, the corrosion results were analyzed by weighing, scanning electron microscope (SEM) and X-ray energy dispersive spectroscopy (EDS). The results showed that Cr2O3/ α-Al2O3 barrier coating partially fell off after high temperature corrosion; The internal oxidation phenomenon of the alloy was not obvious, and the coating can inhibit the oxidation and carburization of the alloy; The mass of the alloy increased after corrosion, and the mass gain of the coated alloy was lower than that of the uncoated alloy.
{"title":"Effect of a Cr2O3/A-Al2O3 Coating on the Corrosion Behavior of Incoloy 800H Alloy in High Temperature Impure Helium","authors":"Haoxiang Li, Weizhen Zheng, B. Du, Huaqiang Yin, Zhihao Hong, Long Wang, Xuedong He, Tengyu Ma, Xingtuan Yang","doi":"10.1115/icone29-90536","DOIUrl":"https://doi.org/10.1115/icone29-90536","url":null,"abstract":"\u0000 In high temperature gas cooled reactor (HTGR), there is a small amount of helium in the primary coolant (ppm level) impure impurities, which will corrode the alloy materials of high temperature reactor and affect the performance of equipment in high temperature environment. The coating preparation technology on the alloy surface can effectively protect the alloy matrix, greatly reduce the corrosion rate of alloy, and improve the reliability and safety of equipment. In this paper, a Cr2O3/α-Al2O3 multilayer barrier coating prepared by RF magnetron sputtering was used to coat Incoloy 800H alloy, and the corrosion behavior of Incoloy 800H alloy with and without coating under selected high-temperature impure helium was investigated. After the experiment, the corrosion results were analyzed by weighing, scanning electron microscope (SEM) and X-ray energy dispersive spectroscopy (EDS). The results showed that Cr2O3/ α-Al2O3 barrier coating partially fell off after high temperature corrosion; The internal oxidation phenomenon of the alloy was not obvious, and the coating can inhibit the oxidation and carburization of the alloy; The mass of the alloy increased after corrosion, and the mass gain of the coated alloy was lower than that of the uncoated alloy.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"13 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83632595","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}
Cheng Cheng, W. Yuanyuan, Pan Yongjie, Ge Yongjun, Wei Zhiguo, Z. Zhihui, Li Zengfen
Based on the safety analysis, the risk of high temperature and radiation are found in the local operation during the automatic welding and vacuum drying of typical spent fuel dry storage system. To enhance the operational safety, a high temperature and radiation protection equipment has been developed through the structural design and numerical analysis and has been applied in demonstration project in China. It is proved by the local monitoring data that in the case of loading spent fuels with a total heat rate of 26kW, with the help of the protection equipment, the highest temperature of the operational area is 60% lower than the case without the equipment in the same environmental conditions. The dose rate in the area can also be 60% lower. The equipment is proved to be of significant help to ensure the safety of operators in high temperature and radiation environments, during both normal operation and equipment failure conditions.
{"title":"Development and Application of High Temperature and Radiation Protection Equipment for Spent Fuel Dry Storage System","authors":"Cheng Cheng, W. Yuanyuan, Pan Yongjie, Ge Yongjun, Wei Zhiguo, Z. Zhihui, Li Zengfen","doi":"10.1115/icone29-92083","DOIUrl":"https://doi.org/10.1115/icone29-92083","url":null,"abstract":"\u0000 Based on the safety analysis, the risk of high temperature and radiation are found in the local operation during the automatic welding and vacuum drying of typical spent fuel dry storage system. To enhance the operational safety, a high temperature and radiation protection equipment has been developed through the structural design and numerical analysis and has been applied in demonstration project in China. It is proved by the local monitoring data that in the case of loading spent fuels with a total heat rate of 26kW, with the help of the protection equipment, the highest temperature of the operational area is 60% lower than the case without the equipment in the same environmental conditions. The dose rate in the area can also be 60% lower. The equipment is proved to be of significant help to ensure the safety of operators in high temperature and radiation environments, during both normal operation and equipment failure conditions.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"13 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91132105","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}
Gui Zhong, Zhang Hui, Wang Wei, Yuan Yueyan, Liu Chao, Li Xiaoqing
With the rapid growth of China’s nuclear power scale, in order to meet the future demand for spent fuel transport, relying on a single road transport mode is far from meeting the transport demand. It is necessary to build a spent fuel multimodal transport system to carry out large-scale spent fuel transport. As a special means of transport for sea transport in spent fuel multimodal transport, China’s first spent fuel transport ship is completely independently designed by China, has passed the empty ship trial voyage, and has also achieved good practice in actual transport. Based on the design requirements of domestic and international laws and regulations for the spent fuel transport ship, and combined with the actual situation of the wharf of domestic nuclear power plant, this paper interprets and analyzes the design ideas of the ship type size, loading layout scheme and safety system of the first spent fuel transport ship in China, in order to provide technical reference for the design and improvement of the spent fuel transport ship in the future.
{"title":"Interpretation and Analysis of Design Idea of the Spent Fuel Transport Ship","authors":"Gui Zhong, Zhang Hui, Wang Wei, Yuan Yueyan, Liu Chao, Li Xiaoqing","doi":"10.1115/icone29-92809","DOIUrl":"https://doi.org/10.1115/icone29-92809","url":null,"abstract":"\u0000 With the rapid growth of China’s nuclear power scale, in order to meet the future demand for spent fuel transport, relying on a single road transport mode is far from meeting the transport demand. It is necessary to build a spent fuel multimodal transport system to carry out large-scale spent fuel transport. As a special means of transport for sea transport in spent fuel multimodal transport, China’s first spent fuel transport ship is completely independently designed by China, has passed the empty ship trial voyage, and has also achieved good practice in actual transport. Based on the design requirements of domestic and international laws and regulations for the spent fuel transport ship, and combined with the actual situation of the wharf of domestic nuclear power plant, this paper interprets and analyzes the design ideas of the ship type size, loading layout scheme and safety system of the first spent fuel transport ship in China, in order to provide technical reference for the design and improvement of the spent fuel transport ship in the future.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"24 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79124455","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}
Dispersed particle fuel is an advanced form of fuel. Due to the need for reactivity control, burnable poison particles and fuel particles are often dispersed in the matrix together. In order to prove the double dispersion mechanism of fuel and burnable poison particles with high calculation accuracy, a random dispersion model of burnable poison particles is constructed in this paper under the conditions of fuel homogenization and random dispersion of fuel particles. Compared with the random dispersion model, direct homogenization of fuel or burnable poison can cause large deviation in the calculation of system eigenvalues according to the MCX calculation. Under the same fuel phase volume, fuel enrichment and burnable poison loading, the maximum deviation can reach 1494pcm. The deviation increases with the increase of the loading mass of the burnable poison in the system, subject to fuel particle diameter of the order ∼100 μm. At a relatively high content of the burnable poison, the deviation decreases with the change of the content of the burnable poison. The calculation results show that the double heterogeneity effect of the system composed of fuel and burnable poison particles cannot be ignored, and the traditional homogenization calculation method must be corrected according to the actual situation. This paper is of valuable reference for the calculation and correction of dispersion fuel homogenization under the condition of strong absorber, and the program development and verification of using a new method to deal with the double heterogeneity effect.
{"title":"Analysis of Double Heterogeneous Effect Under Double Dispersion of Fuel and Burnable Poison Particles","authors":"Anmin Yuan, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Cong Wang, Chaofei Jiang, Shengzhi Yu, Qianglong Wang, Jinrong Qiu","doi":"10.1115/icone29-91463","DOIUrl":"https://doi.org/10.1115/icone29-91463","url":null,"abstract":"\u0000 Dispersed particle fuel is an advanced form of fuel. Due to the need for reactivity control, burnable poison particles and fuel particles are often dispersed in the matrix together. In order to prove the double dispersion mechanism of fuel and burnable poison particles with high calculation accuracy, a random dispersion model of burnable poison particles is constructed in this paper under the conditions of fuel homogenization and random dispersion of fuel particles. Compared with the random dispersion model, direct homogenization of fuel or burnable poison can cause large deviation in the calculation of system eigenvalues according to the MCX calculation. Under the same fuel phase volume, fuel enrichment and burnable poison loading, the maximum deviation can reach 1494pcm. The deviation increases with the increase of the loading mass of the burnable poison in the system, subject to fuel particle diameter of the order ∼100 μm. At a relatively high content of the burnable poison, the deviation decreases with the change of the content of the burnable poison. The calculation results show that the double heterogeneity effect of the system composed of fuel and burnable poison particles cannot be ignored, and the traditional homogenization calculation method must be corrected according to the actual situation. This paper is of valuable reference for the calculation and correction of dispersion fuel homogenization under the condition of strong absorber, and the program development and verification of using a new method to deal with the double heterogeneity effect.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"127 2 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79579522","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}
This paper takes a certain nuclear power plant (NPP) which consists of two 1000 MWe PWR units as the research object, and summarizes various fuel management strategies experienced since it started commercial operation in 2002 and 2003. These fuel management strategies include: 1) high-leakage annual refueling, refueling fuel enrichment is 3.2% and cycle length reaches about 270 EFPD; 2) fuel type mixed refueling (AFA2G and AFA3G mixed), refueling fuel enrichment increases from 3.2% to 3.7% and cycle length reaches about 320 EFPD; 3) low-leakage 1/4 refueling, refueling fuel enrichment increases from 3.7% to 4.2% and cycle length reaches about 316 EFPD that fuel economy has been greatly improved; 4) low-leakage 18-months refueling, refueling fuel enrichment increases from 4.2% to 4.45% and the refueling cycle has been extended from annual refueling to an average of 16 months; 5) two-enrichment refueling, refueling fuel enrichment is extended from single 4.45% to two enrichment 4.45% and 4.00%, which improves the flexibility of fuel management to well meet the load shedding needs. This paper reviews each fuel management strategy’s general refueling pattern, main design parameters and actual operating parameters of the core, fuel economy and the feedback of related problems, finally further suggests a few optimizations of future fuel management strategies.
{"title":"Summary of the History of Improvement and Optimization of Fuel Management Strategies for Two 1000 MWe PWR Units","authors":"Zhou Xiaoling, Xu Zhixian, Zhao Bingquan, Li Wen, Zhong Shengdong, Gao Jinghui","doi":"10.1115/icone29-92954","DOIUrl":"https://doi.org/10.1115/icone29-92954","url":null,"abstract":"\u0000 This paper takes a certain nuclear power plant (NPP) which consists of two 1000 MWe PWR units as the research object, and summarizes various fuel management strategies experienced since it started commercial operation in 2002 and 2003. These fuel management strategies include:\u0000 1) high-leakage annual refueling, refueling fuel enrichment is 3.2% and cycle length reaches about 270 EFPD;\u0000 2) fuel type mixed refueling (AFA2G and AFA3G mixed), refueling fuel enrichment increases from 3.2% to 3.7% and cycle length reaches about 320 EFPD;\u0000 3) low-leakage 1/4 refueling, refueling fuel enrichment increases from 3.7% to 4.2% and cycle length reaches about 316 EFPD that fuel economy has been greatly improved;\u0000 4) low-leakage 18-months refueling, refueling fuel enrichment increases from 4.2% to 4.45% and the refueling cycle has been extended from annual refueling to an average of 16 months;\u0000 5) two-enrichment refueling, refueling fuel enrichment is extended from single 4.45% to two enrichment 4.45% and 4.00%, which improves the flexibility of fuel management to well meet the load shedding needs.\u0000 This paper reviews each fuel management strategy’s general refueling pattern, main design parameters and actual operating parameters of the core, fuel economy and the feedback of related problems, finally further suggests a few optimizations of future fuel management strategies.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"129 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73762617","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 application of the dual-cooled annular fuel element can significantly improve the safety and economy of current pressurized water reactors. Due to the geometric differences, the fuel relocation caused by the fuel cracking in annular rods was much more complex and influential on thermal-hydraulic performance than that in solid rods. In this research, the Discrete Element Method (DEM) was applied to perform the simulation of fuel fragment relocation in the annular fuel rod under both long-term normal operation and LOCA conditions, in order to get deep insights into the fuel relocation mechanisms and develop the mathematical relocation model. Under normal operations, it was found that the radial fuel relocation was bidirectional of both inward and outward, resulting in the radial size reduction of both internal and external gas gaps. The maximum reduction of total gaps was about 58% of the as-fabricated value, and the maximum allowable recovery fraction of fuel relocation was about 55%. Under LOCA conditions, the ballooning of the cladding was full considered in the fuel relocation. As a consequence, the substantial axial fuel relocation was found, which resulting a size reduction of active fuel length and a local fuel accumulation at the position of ballooning.
{"title":"Research on Cracked Fuel Relocation of Dual-Cooled Annular Fuel Element Under Normal and LOCA Conditions","authors":"Yangbin Deng, Yuan Yin","doi":"10.1115/icone29-90755","DOIUrl":"https://doi.org/10.1115/icone29-90755","url":null,"abstract":"\u0000 The application of the dual-cooled annular fuel element can significantly improve the safety and economy of current pressurized water reactors. Due to the geometric differences, the fuel relocation caused by the fuel cracking in annular rods was much more complex and influential on thermal-hydraulic performance than that in solid rods. In this research, the Discrete Element Method (DEM) was applied to perform the simulation of fuel fragment relocation in the annular fuel rod under both long-term normal operation and LOCA conditions, in order to get deep insights into the fuel relocation mechanisms and develop the mathematical relocation model. Under normal operations, it was found that the radial fuel relocation was bidirectional of both inward and outward, resulting in the radial size reduction of both internal and external gas gaps. The maximum reduction of total gaps was about 58% of the as-fabricated value, and the maximum allowable recovery fraction of fuel relocation was about 55%. Under LOCA conditions, the ballooning of the cladding was full considered in the fuel relocation. As a consequence, the substantial axial fuel relocation was found, which resulting a size reduction of active fuel length and a local fuel accumulation at the position of ballooning.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"143 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73978261","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}
Yinghong Li, Z. Lv, C. Li, Yuyu Lin, Shaofang Lin, Zhiyi Cai, Yong-jun Deng, Lihong Nie
Manufacturing defects of fuel rod end plug during welding affect fuel reliability. Failure of ring welding or sealing welding of fuel rod end plug during operation will cause fission gas to enter primary coolant of reactor. In order to determine the sensitivity of the influence of relevant characteristic parameters on the performance of fuel rods during end plug welding, based on the Quality Function Deployment method (QFD) and taking tungsten-inert-gas arc welding (TIG) as an example, the characteristic parameters of fuel rod end plug welding are analyzed. Combined with the experimental results, a correlation matrix between welding parameters and welding performance is constructed by LIKERT scale method with focus on the main welding performance criteria such as welding joint size, color, depth of fusion, metallography (bloating, porosity, inclusion, grain boundary separation, etc.), oxidation resistance, etc. And after rating its correlation degree and importance degree, the relevant House of Quality of end plug welding is constructed, and the key impact parameters are identified. Based on the above analysis, some feasible optimization and improvement proposals are put forward for the quality supervision and welding process of fuel element manufacturing factory.
{"title":"Key Impact Factors Analysis of Fuel Rod End Plug Welding Based on QFD","authors":"Yinghong Li, Z. Lv, C. Li, Yuyu Lin, Shaofang Lin, Zhiyi Cai, Yong-jun Deng, Lihong Nie","doi":"10.1115/icone29-92803","DOIUrl":"https://doi.org/10.1115/icone29-92803","url":null,"abstract":"\u0000 Manufacturing defects of fuel rod end plug during welding affect fuel reliability. Failure of ring welding or sealing welding of fuel rod end plug during operation will cause fission gas to enter primary coolant of reactor. In order to determine the sensitivity of the influence of relevant characteristic parameters on the performance of fuel rods during end plug welding, based on the Quality Function Deployment method (QFD) and taking tungsten-inert-gas arc welding (TIG) as an example, the characteristic parameters of fuel rod end plug welding are analyzed. Combined with the experimental results, a correlation matrix between welding parameters and welding performance is constructed by LIKERT scale method with focus on the main welding performance criteria such as welding joint size, color, depth of fusion, metallography (bloating, porosity, inclusion, grain boundary separation, etc.), oxidation resistance, etc. And after rating its correlation degree and importance degree, the relevant House of Quality of end plug welding is constructed, and the key impact parameters are identified. Based on the above analysis, some feasible optimization and improvement proposals are put forward for the quality supervision and welding process of fuel element manufacturing factory.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"2 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74364125","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}
In the core of pressurized water nuclear reactor, coolant flow-induced vibration of Grid to rod fretting (GTRF) is the dominant factor leading to fuel rod damage. pre-oxidization treatment of zirconium cladding forming a ceramic layer on its surface is the main way to reduce the GTRF wear. In this paper, the growth law of CZ2 alloy cladding pre-oxidization zirconia ceramic layer formed in air was studied. The micro-hardness and elastic modulus of CZ2 alloy cladding and zirconia ceramic layer were measured by in-situ nano-mechanical testing system., while the morphology of these pre-oxidization zirconia ceramic layer were observed by scanning electron microscope. The fretting wear properties of the pre-oxidization zirconia ceramic layer were studied by high temperature and high pressure fretting wear tests. The results show that the pre-oxidization zirconia ceramic layer growth law of CZ2 alloy cladding at 560°C and 600°C is consistent, and the pre-oxidization zirconia ceramic layer are compact and crack-free. The pre-oxidization zirconia ceramic layer can improve the fretting wear resistance of CZ2 alloy cladding at high temperature and high pressure, and the maximum wear depth were reduced by 80%.
{"title":"Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding","authors":"Guocheng Sun, Shi Lin, Xu Wang, Liu-tao Chen","doi":"10.1115/icone29-93804","DOIUrl":"https://doi.org/10.1115/icone29-93804","url":null,"abstract":"\u0000 In the core of pressurized water nuclear reactor, coolant flow-induced vibration of Grid to rod fretting (GTRF) is the dominant factor leading to fuel rod damage. pre-oxidization treatment of zirconium cladding forming a ceramic layer on its surface is the main way to reduce the GTRF wear. In this paper, the growth law of CZ2 alloy cladding pre-oxidization zirconia ceramic layer formed in air was studied. The micro-hardness and elastic modulus of CZ2 alloy cladding and zirconia ceramic layer were measured by in-situ nano-mechanical testing system., while the morphology of these pre-oxidization zirconia ceramic layer were observed by scanning electron microscope. The fretting wear properties of the pre-oxidization zirconia ceramic layer were studied by high temperature and high pressure fretting wear tests. The results show that the pre-oxidization zirconia ceramic layer growth law of CZ2 alloy cladding at 560°C and 600°C is consistent, and the pre-oxidization zirconia ceramic layer are compact and crack-free. The pre-oxidization zirconia ceramic layer can improve the fretting wear resistance of CZ2 alloy cladding at high temperature and high pressure, and the maximum wear depth were reduced by 80%.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"86 8","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72394323","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}
Q. Y. Lv, Libin Zhang, Minli Chen, Changyuan Gao, Yang Xu, Liu-tao Chen, J. Tan
This paper conducts in-depth research on zirconium alloys by combining results of out-of-pile corrosion and creep performance with microstructual and micro-chemical analysis using state-of-the-art (S)TEM, EDX and EBSD. The mechanism of different heat treatment processes on the macroscopic properties of zirconium alloys is explained from the microscopic level. By comparing various Zr-Sn-Nb alloys with different intermediate temperatures, it is discovered that creep resistance becomes better and the corrosion resistance becomes worse. It is found that average grain size increases gradually with increasing intermediate temperature, creep deformation is related with grain boundary slip, so the smaller grain size, the faster creep rate. In alloys with Nb content less than its solid solution limit in zirconium, when increasing the intermediate annealing temperature, there are fewer Nb-rich Zr-Fe-Cr-Nb second phase particles (SPPs) but more Cr-rich Zr-Fe-Cr-Nb SPPs, so the amount of Nb in solid solution in the matrix increases, which lead to better creep resistance due to solid solution strengthening and lower diffusion coefficient, however, with higher Nb solid solution content, there is more tetragonal to monoclinic oxide phase transition, which causes more cracking in the oxide and increases the corrosion rate.
{"title":"Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties","authors":"Q. Y. Lv, Libin Zhang, Minli Chen, Changyuan Gao, Yang Xu, Liu-tao Chen, J. Tan","doi":"10.1115/icone29-93770","DOIUrl":"https://doi.org/10.1115/icone29-93770","url":null,"abstract":"\u0000 This paper conducts in-depth research on zirconium alloys by combining results of out-of-pile corrosion and creep performance with microstructual and micro-chemical analysis using state-of-the-art (S)TEM, EDX and EBSD. The mechanism of different heat treatment processes on the macroscopic properties of zirconium alloys is explained from the microscopic level.\u0000 By comparing various Zr-Sn-Nb alloys with different intermediate temperatures, it is discovered that creep resistance becomes better and the corrosion resistance becomes worse. It is found that average grain size increases gradually with increasing intermediate temperature, creep deformation is related with grain boundary slip, so the smaller grain size, the faster creep rate. In alloys with Nb content less than its solid solution limit in zirconium, when increasing the intermediate annealing temperature, there are fewer Nb-rich Zr-Fe-Cr-Nb second phase particles (SPPs) but more Cr-rich Zr-Fe-Cr-Nb SPPs, so the amount of Nb in solid solution in the matrix increases, which lead to better creep resistance due to solid solution strengthening and lower diffusion coefficient, however, with higher Nb solid solution content, there is more tetragonal to monoclinic oxide phase transition, which causes more cracking in the oxide and increases the corrosion rate.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"7 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90134430","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}
Glass solidification is a favorable treatment method for high level liquid waste (HLLW) from spent fuel reprocessing in industrial application, and the presence of palladium (Pd) in HLLW may seriously affect the glass solidification process. Ferrocyanide with a perovskite-like face-centered cubic structure has strong adsorption affinity towards Pd. In this study, silica-based composite KMnFC/SiO2 was prepared by pore crystallization of potassium manganese ferrocyanide (KMnFC) into porous SiO2. A series of characterization of the synthesized adsorbent were carried out such as XRD, TG-DTA, and SEM-EDS. It was verified that the adsorbent was successfully prepared and it has good Microscopic structure along with element distribution. A series of adsorption experiments were carried out. The adsorption of Pd is not easily affected by the concentration of nitric acid, which shows good acid resistance. Through the adsorption isotherm and adsorption kinetic curve, it is proved that the adsorption process of Pd by KMnFC/SiO2 is chemical monolayer adsorption. The adsorbent has strong adsorption selectivity for Pd in multi-ionic solution. Under the condition of complete adsorption of Pd, the adsorption rate of the adsorbent for other elements except Ru is less than 20%.
{"title":"Study on Separation of Palladium From High Level Liquid Waste by Potassium Manganese Ferrocyanide","authors":"Tian-Jiao Qi, Hongji Sang, Cong Mao, Yueying Wen, Jipu Hu, Yan Wu","doi":"10.1115/icone29-92971","DOIUrl":"https://doi.org/10.1115/icone29-92971","url":null,"abstract":"\u0000 Glass solidification is a favorable treatment method for high level liquid waste (HLLW) from spent fuel reprocessing in industrial application, and the presence of palladium (Pd) in HLLW may seriously affect the glass solidification process. Ferrocyanide with a perovskite-like face-centered cubic structure has strong adsorption affinity towards Pd. In this study, silica-based composite KMnFC/SiO2 was prepared by pore crystallization of potassium manganese ferrocyanide (KMnFC) into porous SiO2. A series of characterization of the synthesized adsorbent were carried out such as XRD, TG-DTA, and SEM-EDS. It was verified that the adsorbent was successfully prepared and it has good Microscopic structure along with element distribution.\u0000 A series of adsorption experiments were carried out. The adsorption of Pd is not easily affected by the concentration of nitric acid, which shows good acid resistance. Through the adsorption isotherm and adsorption kinetic curve, it is proved that the adsorption process of Pd by KMnFC/SiO2 is chemical monolayer adsorption. The adsorbent has strong adsorption selectivity for Pd in multi-ionic solution. Under the condition of complete adsorption of Pd, the adsorption rate of the adsorbent for other elements except Ru is less than 20%.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"16 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83807286","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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