核电厂乏燃料池热流与事故分析技术之建立与应用
发布时间：2018-11-03 16:41
【摘要】：乏燃料池作为过渡期暂时性的乏燃料储存方式，在2011年3月11日本福岛核泄漏事故后，其安全性作为新的议题引起人们广泛关注，因此需要对核电厂乏燃料池丧失事故进行细致的研究。 本文以系统程式RELAP5/MOD3为分析工具，建立核电厂乏燃料池模式，模拟全池热水流行为。模式根据退出燃料的周期来划分节点，详细分析了包含最新退出燃料的格架区域并加入辐射传热模式。按美国核管会标准审查方案附的衰变热功率计算式ABS-92计算核电厂乏燃料池中燃料产生的衰变热。 基于已建立的乏燃料池模型，模拟了乏燃料池及冷却系统正常运转下的稳态工况，以及乏燃料池冷却丧失下的瞬态工况。估算丧失冷却事故发生后燃料裸露及包壳温度升至2200°F的时间。分析了辐射传热模式、在放射性物质外泄前洒水以及细分hot channel、格架外bypass区节点数划分对燃料温度变化趋势的影响。 分析计算结果显示，模式能够模拟乏燃料池及其冷却系统正常运行下的稳态工况，建立乏燃料池内的自然对流冷却机制；事故发生后燃料裸露所需的时间为17.87天，燃料包壳温度达到2200°F的时间为19.14天；辐射传热模式将燃料包壳温度到达2200°F的时间延迟了8.97小时；NEI06-12所建议的200gpm洒水量需要8630（s2.4hour）将燃料温度由726.9°C降到100°C，如果将洒水量减至100gpm则需要远大于两倍时间的36170s（10.05hour）将燃料温度由726.9°C降到100°C；功率密度最高的区域节点划分更细时，燃料包壳温度到达2200°F的时间会提前6.3小时；格架外bypass区节点划分更细时，燃料包壳温度到达2200°F的时间会延后0.89小时。
[Abstract]:As a temporary storage mode of spent fuel during the transitional period, the safety of spent fuel pool has aroused widespread concern after the Fukushima nuclear accident on March 11, 2011. Therefore, it is necessary to study the loss of spent fuel pool in nuclear power plant. In this paper, the model of spent fuel pool in nuclear power plant is established by using the system program RELAP5/MOD3 as an analysis tool, and the hot water prevalence of the whole pool is simulated. The model is divided into nodes according to the period of exit fuel, the grid region including the latest exit fuel is analyzed in detail and the radiation heat transfer mode is added. The decay heat produced by the spent fuel cell of nuclear power plant is calculated by ABS-92 formula according to the decay heat power formula attached to the standard review program of the American Nuclear Regulatory Commission. Based on the established model of spent fuel tank, the steady state of spent fuel tank and cooling system under normal operation and the transient condition of spent fuel tank under cooling loss are simulated. The time of fuel exposure and cladding temperature rising to 2200 掳F after the loss of cooling accident was estimated. The effects of radiation heat transfer model, sprinkling water before radioactive material release and subdivision of bypass node points on fuel temperature change are analyzed. The results show that the model can simulate the steady state of the spent fuel tank and its cooling system under normal operation and establish the natural convection cooling mechanism in the spent fuel tank. After the accident, the time of fuel exposure is 17.87 days, the time of fuel cladding temperature reaching 2200 掳F is 19.14 days, the time of fuel cladding temperature reaching 2200 掳F is delayed by radiation heat transfer mode, the time of fuel cladding temperature reaching 2200 掳F is delayed by 8.97 hours. The 200gpm sprinkler recommended by NEI06-12 requires 8630 (s2.4hour) to reduce the fuel temperature from 726.9 掳C to 100 掳C. if the sprinkler is reduced to 100gpm, it will take 36170s (10.05hour) of much more than twice the time to reduce the fuel temperature from 726.9 掳C to 100 掳C. The time of fuel cladding temperature reaching 2200 掳F will be advanced by 6.3 hours when the highest power density zone node is further divided, and the time of fuel cladding temperature reaching 2200 掳F will be delayed by 0.89 hours when the node division of bypass zone outside the grid is more detailed.
【学位授予单位】：上海交通大学
【学位级别】：硕士
【学位授予年份】：2013
【分类号】：TL364.4
本文编号：2308345
[Abstract]:As a temporary storage mode of spent fuel during the transitional period, the safety of spent fuel pool has aroused widespread concern after the Fukushima nuclear accident on March 11, 2011. Therefore, it is necessary to study the loss of spent fuel pool in nuclear power plant. In this paper, the model of spent fuel pool in nuclear power plant is established by using the system program RELAP5/MOD3 as an analysis tool, and the hot water prevalence of the whole pool is simulated. The model is divided into nodes according to the period of exit fuel, the grid region including the latest exit fuel is analyzed in detail and the radiation heat transfer mode is added. The decay heat produced by the spent fuel cell of nuclear power plant is calculated by ABS-92 formula according to the decay heat power formula attached to the standard review program of the American Nuclear Regulatory Commission. Based on the established model of spent fuel tank, the steady state of spent fuel tank and cooling system under normal operation and the transient condition of spent fuel tank under cooling loss are simulated. The time of fuel exposure and cladding temperature rising to 2200 掳F after the loss of cooling accident was estimated. The effects of radiation heat transfer model, sprinkling water before radioactive material release and subdivision of bypass node points on fuel temperature change are analyzed. The results show that the model can simulate the steady state of the spent fuel tank and its cooling system under normal operation and establish the natural convection cooling mechanism in the spent fuel tank. After the accident, the time of fuel exposure is 17.87 days, the time of fuel cladding temperature reaching 2200 掳F is 19.14 days, the time of fuel cladding temperature reaching 2200 掳F is delayed by radiation heat transfer mode, the time of fuel cladding temperature reaching 2200 掳F is delayed by 8.97 hours. The 200gpm sprinkler recommended by NEI06-12 requires 8630 (s2.4hour) to reduce the fuel temperature from 726.9 掳C to 100 掳C. if the sprinkler is reduced to 100gpm, it will take 36170s (10.05hour) of much more than twice the time to reduce the fuel temperature from 726.9 掳C to 100 掳C. The time of fuel cladding temperature reaching 2200 掳F will be advanced by 6.3 hours when the highest power density zone node is further divided, and the time of fuel cladding temperature reaching 2200 掳F will be delayed by 0.89 hours when the node division of bypass zone outside the grid is more detailed.
【学位授予单位】：上海交通大学
【学位级别】：硕士
【学位授予年份】：2013
【分类号】：TL364.4
【参考文献】
相关硕士学位论文 前2条
1 殷煜皓;AP1000先进核电厂大破口RELAP5建模及特性分析[D];上海交通大学;2012年
2 张楠;基于RELAP5的核动力装置故障仿真平台研究[D];哈尔滨工程大学;2009年
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