Accident-tolerant fuel(ATF)has attracted considerable research attention since the 2011 Fukushima nuclear disaster.To improve the accident tolerance of the fuel-cladding systems in the current light-water reactors,it ...Accident-tolerant fuel(ATF)has attracted considerable research attention since the 2011 Fukushima nuclear disaster.To improve the accident tolerance of the fuel-cladding systems in the current light-water reactors,it is proposed to develop and deploy(1)an enhanced Zrbased alloy or coated zircaloy for the fuel cladding,(2)alternative cladding materials with better accident tolerance,and(3)alternative fuels with enhanced accident tolerance and/or a higher U density.This review presents the features of the current UO2-zircaloy system.Different techniques and characters to develop coating materials and enhanced Zr-based alloys are summarized.The features of several selected alternative fuels and cladding materials are reviewed and discussed.The neutronic evaluations of alternative fuel-cladding systems are analyzed.It is expected that one or more types of ATF-cladding systems discussed in the present review will be implemented in commercial reactors.展开更多
In resonance with the Fukushima Daiichi Nuclear Power Plant accident lesson, a novel fuel design to enhance safety regarding severe accident scenarios has become increasingly appreciated in the nuclear power industry....In resonance with the Fukushima Daiichi Nuclear Power Plant accident lesson, a novel fuel design to enhance safety regarding severe accident scenarios has become increasingly appreciated in the nuclear power industry. This research focuses on analysis of the neutronic properties of a silicon carbide(SiC) cladding fuel assembly, which provides a greater safety margin as a type of accident-tolerant fuel for pressurized water reactors. The general physical performance of SiC cladding is explored to ascertain its neutronic performance. The neutron spectrum, accumulation of ^(239)Pu, physical characteristics,temperature reactivity coefficient, and power distribution are analyzed. Furthermore, the influences of a burnable poison rod and enrichment are explored. SiC cladding assemblies show a softer neutron spectrum and flatter power distribution than conventional Zr alloy cladding fuel assemblies. Lower enrichment fuel is required when SiC cladding is adopted. However, the positive reactivity coefficient associated with the SiC material remains to be offset. The results reveal that SiC cladding assemblies show broad agreement with the neutronic performance of conventional Zr alloy cladding fuel. In the meantime, its unique physical characteristics can lead to improved safety and economy.展开更多
The subject of this study is the oxidation of fuel rod cladding made of material Zr1Nb(0.1% O) in steam at temperatures in the range of 660℃ to 1200℃ with a surface in the initial state (after manufacturing - grindi...The subject of this study is the oxidation of fuel rod cladding made of material Zr1Nb(0.1% O) in steam at temperatures in the range of 660℃ to 1200℃ with a surface in the initial state (after manufacturing - grinding) and after additional chemical etching. The changes in the microstructure of tubes due to the interaction with steam were investigated. A comparison was made between the oxidation rate of this material (weight gain) and the data on the oxidation of other alloys for nuclear power plants. The oxidation rate of Zr1Nb(0.1% O) is close to the oxidation rate of other zirconium alloys. It is shown that after chemical treatment of the surface of the samples there is a more even growth of oxide films, and they have a smaller thickness for the same time of exposure than after mechanical grinding. Surface treatment before oxidation also affects the change of microstructure of samples when heated to high temperatures.展开更多
Accident at Fukushima Dai-ichi nuclear power plant significantly affected the nuclear industry at time when everybody was expecting the so called nuclear renaissance. There is no question that the accident has at leas...Accident at Fukushima Dai-ichi nuclear power plant significantly affected the nuclear industry at time when everybody was expecting the so called nuclear renaissance. There is no question that the accident has at least slowed it down. Research on this accident is taking place all over the world, in this paper, we present the findings of research on Fukushima nuclear power plant accident in relation to the Czech Republic. The paper focuses on the analysis of human performance during the accident. Lessons learned from the accident and main human errors are presented. First, the brief factors affecting the human performance are discussed. They are followed by the short description of activities on units 1-3. The key human errors in the accident mitigation are then identified. On unit 1, the fuel damage was probably impossible to prevent, however, on units 2 and 3, it could be probably prevented.展开更多
The transient multiphysics models were updated in CAMPUS to evaluate the accident-tolerant fuel performance under accident conditions.CAMPUS is a fuel performance code developed based on COMSOL.The simulated results o...The transient multiphysics models were updated in CAMPUS to evaluate the accident-tolerant fuel performance under accident conditions.CAMPUS is a fuel performance code developed based on COMSOL.The simulated results of the UO_(2)–Zircaloy fuel performance under accident conditions were compared with those of the FRAPTRAN code and the experimental data to verify the correctness of the updated CAMPUS.Subsequently,multiphysics models of the UO_(2)–BeO fuel and composite SiC coated with Cr(SiC_(f)/SiC-Cr)cladding were implemented in CAMPUS.Finally,the fuel performance of the three types of fuel cladding systems under Loss of Coolant Accident(LOCA)and Reactivity Insertion Accident(RIA)conditions was evaluated and compared,including the temperature distribution,stress distribution,pressure evolution,and cladding failure time.The results showed that the fuel temperature of the UO_(2) fuel under accident conditions without pre-irradiation was lower after being combined with SiC_(f)/SiC-Cr cladding.Moreover,the centerline and outer surface temperatures of the UO_(2)–BeO fuel combined with SiC_(f)/SiC-Cr cladding reduced further under accident conditions.The cladding temperature increased after the combination with the SiC_(f)/SiC-Cr cladding under accident conditions with pre-irradiation.In addition,the use of SiC_(f)/SiC-Cr cladding significantly reduced the cladding hoop strain and plenum pressure.展开更多
Steam explosion is one of the crucial and poorly understood phenomena which may occur during severe accident scenario and may lead to containment failure. In spite of several experimental and analytical studies, the r...Steam explosion is one of the crucial and poorly understood phenomena which may occur during severe accident scenario and may lead to containment failure. In spite of several experimental and analytical studies, the root cause of steam explosion has not been understood. Recent claims in the literature suggest that the presence of fine fragmentation during steam explosion causes its occurrence. In order to investigate this and understand the root cause of steam explosion, series of experiments were performed with 50 g to 2500 g of CaO-B<sub>2</sub>O<sub>3</sub>, a corium simulant in 4.5 litre of water. It was observed that steam explosion may occur even in the absence of fine fragments, which is contrary to the claims in the literature. To investigate further, conversion efficiency analysis was performed. This suggested that the amount of thermal energy converted to mechanical energy is more important deciding factor in explaining the occurrence of steam explosion. The present study discusses the importance of conversion efficiency in deciding steam explosion and also gives a new perspective to look at steam explosion phenomenology.展开更多
城市埋地燃气(主要包括天然气、煤气)管网在运行中会受到复杂环境因素和人为因素的影响,如果发生失效,就会直接威胁着管道沿线附近人员生命和国家财产的安全,因此有必要对燃气管道进行可靠性分析。失效树分析(Fault Tree Analysis)是一...城市埋地燃气(主要包括天然气、煤气)管网在运行中会受到复杂环境因素和人为因素的影响,如果发生失效,就会直接威胁着管道沿线附近人员生命和国家财产的安全,因此有必要对燃气管道进行可靠性分析。失效树分析(Fault Tree Analysis)是一种已被广泛应用的可靠性分析方法。文章选取失效树分析法对引起城市埋地燃气管网失效的各方面因素进行了全面地系统分析,建立了以燃气管网失效为顶事件,包含了116个基本事件的城市埋地燃气管网失效树。通过逻辑运算,得到了失效树的287个最小割集,并通过实例计算与分析对上述失效树进行了验证。通过对最小割集的分析,得到了影响城市埋地燃气管网可靠性的各影响因素的逻辑关系。结果表明,第三方破坏、腐蚀、制造缺陷等是影响城市埋地燃气管网可靠性最主要的因素,并提出了相应的措施以提高燃气管网的可靠性。展开更多
基金supported by the National Key Research and Development Program of China(No.2018YFB1900405)the National Natural Science Foundation of China(No.11775316)+3 种基金the Tip-top Scientific and Technical Innovative Youth Talents of Guangdong Special Support Program(No.2016TQ03N575)the Fundamental Research Funds for the Central Universities(No.19lgpy299)the Science and Technology Planning Project of Guangdong Province,China(No.2019A050510022)the Nuclear Power Institute of China(No.HT-ATF-14-2018001)
文摘Accident-tolerant fuel(ATF)has attracted considerable research attention since the 2011 Fukushima nuclear disaster.To improve the accident tolerance of the fuel-cladding systems in the current light-water reactors,it is proposed to develop and deploy(1)an enhanced Zrbased alloy or coated zircaloy for the fuel cladding,(2)alternative cladding materials with better accident tolerance,and(3)alternative fuels with enhanced accident tolerance and/or a higher U density.This review presents the features of the current UO2-zircaloy system.Different techniques and characters to develop coating materials and enhanced Zr-based alloys are summarized.The features of several selected alternative fuels and cladding materials are reviewed and discussed.The neutronic evaluations of alternative fuel-cladding systems are analyzed.It is expected that one or more types of ATF-cladding systems discussed in the present review will be implemented in commercial reactors.
基金supported by the National Natural Science Foundation of China(No.11675057)the Fundamental Research Funds for the Central Universities(No.2017ZD100)
文摘In resonance with the Fukushima Daiichi Nuclear Power Plant accident lesson, a novel fuel design to enhance safety regarding severe accident scenarios has become increasingly appreciated in the nuclear power industry. This research focuses on analysis of the neutronic properties of a silicon carbide(SiC) cladding fuel assembly, which provides a greater safety margin as a type of accident-tolerant fuel for pressurized water reactors. The general physical performance of SiC cladding is explored to ascertain its neutronic performance. The neutron spectrum, accumulation of ^(239)Pu, physical characteristics,temperature reactivity coefficient, and power distribution are analyzed. Furthermore, the influences of a burnable poison rod and enrichment are explored. SiC cladding assemblies show a softer neutron spectrum and flatter power distribution than conventional Zr alloy cladding fuel assemblies. Lower enrichment fuel is required when SiC cladding is adopted. However, the positive reactivity coefficient associated with the SiC material remains to be offset. The results reveal that SiC cladding assemblies show broad agreement with the neutronic performance of conventional Zr alloy cladding fuel. In the meantime, its unique physical characteristics can lead to improved safety and economy.
文摘The subject of this study is the oxidation of fuel rod cladding made of material Zr1Nb(0.1% O) in steam at temperatures in the range of 660℃ to 1200℃ with a surface in the initial state (after manufacturing - grinding) and after additional chemical etching. The changes in the microstructure of tubes due to the interaction with steam were investigated. A comparison was made between the oxidation rate of this material (weight gain) and the data on the oxidation of other alloys for nuclear power plants. The oxidation rate of Zr1Nb(0.1% O) is close to the oxidation rate of other zirconium alloys. It is shown that after chemical treatment of the surface of the samples there is a more even growth of oxide films, and they have a smaller thickness for the same time of exposure than after mechanical grinding. Surface treatment before oxidation also affects the change of microstructure of samples when heated to high temperatures.
文摘Accident at Fukushima Dai-ichi nuclear power plant significantly affected the nuclear industry at time when everybody was expecting the so called nuclear renaissance. There is no question that the accident has at least slowed it down. Research on this accident is taking place all over the world, in this paper, we present the findings of research on Fukushima nuclear power plant accident in relation to the Czech Republic. The paper focuses on the analysis of human performance during the accident. Lessons learned from the accident and main human errors are presented. First, the brief factors affecting the human performance are discussed. They are followed by the short description of activities on units 1-3. The key human errors in the accident mitigation are then identified. On unit 1, the fuel damage was probably impossible to prevent, however, on units 2 and 3, it could be probably prevented.
基金support from the General Universities Characteristic Innovation Project of Guangdong Province(No.2022KTSCX006)Sichuan Science and Technology Program(No.2019ZDZX0001)。
文摘The transient multiphysics models were updated in CAMPUS to evaluate the accident-tolerant fuel performance under accident conditions.CAMPUS is a fuel performance code developed based on COMSOL.The simulated results of the UO_(2)–Zircaloy fuel performance under accident conditions were compared with those of the FRAPTRAN code and the experimental data to verify the correctness of the updated CAMPUS.Subsequently,multiphysics models of the UO_(2)–BeO fuel and composite SiC coated with Cr(SiC_(f)/SiC-Cr)cladding were implemented in CAMPUS.Finally,the fuel performance of the three types of fuel cladding systems under Loss of Coolant Accident(LOCA)and Reactivity Insertion Accident(RIA)conditions was evaluated and compared,including the temperature distribution,stress distribution,pressure evolution,and cladding failure time.The results showed that the fuel temperature of the UO_(2) fuel under accident conditions without pre-irradiation was lower after being combined with SiC_(f)/SiC-Cr cladding.Moreover,the centerline and outer surface temperatures of the UO_(2)–BeO fuel combined with SiC_(f)/SiC-Cr cladding reduced further under accident conditions.The cladding temperature increased after the combination with the SiC_(f)/SiC-Cr cladding under accident conditions with pre-irradiation.In addition,the use of SiC_(f)/SiC-Cr cladding significantly reduced the cladding hoop strain and plenum pressure.
文摘Steam explosion is one of the crucial and poorly understood phenomena which may occur during severe accident scenario and may lead to containment failure. In spite of several experimental and analytical studies, the root cause of steam explosion has not been understood. Recent claims in the literature suggest that the presence of fine fragmentation during steam explosion causes its occurrence. In order to investigate this and understand the root cause of steam explosion, series of experiments were performed with 50 g to 2500 g of CaO-B<sub>2</sub>O<sub>3</sub>, a corium simulant in 4.5 litre of water. It was observed that steam explosion may occur even in the absence of fine fragments, which is contrary to the claims in the literature. To investigate further, conversion efficiency analysis was performed. This suggested that the amount of thermal energy converted to mechanical energy is more important deciding factor in explaining the occurrence of steam explosion. The present study discusses the importance of conversion efficiency in deciding steam explosion and also gives a new perspective to look at steam explosion phenomenology.
文摘城市埋地燃气(主要包括天然气、煤气)管网在运行中会受到复杂环境因素和人为因素的影响,如果发生失效,就会直接威胁着管道沿线附近人员生命和国家财产的安全,因此有必要对燃气管道进行可靠性分析。失效树分析(Fault Tree Analysis)是一种已被广泛应用的可靠性分析方法。文章选取失效树分析法对引起城市埋地燃气管网失效的各方面因素进行了全面地系统分析,建立了以燃气管网失效为顶事件,包含了116个基本事件的城市埋地燃气管网失效树。通过逻辑运算,得到了失效树的287个最小割集,并通过实例计算与分析对上述失效树进行了验证。通过对最小割集的分析,得到了影响城市埋地燃气管网可靠性的各影响因素的逻辑关系。结果表明,第三方破坏、腐蚀、制造缺陷等是影响城市埋地燃气管网可靠性最主要的因素,并提出了相应的措施以提高燃气管网的可靠性。
