{"title":"AP1000反应堆典型燃料组件中MOX(U,Th)O2燃料应用的热工水力学评估","authors":"Caio J.C.M.R. Cunha, F. A. Lima, D. Rodríguez","doi":"10.1504/ijnest.2020.10034460","DOIUrl":null,"url":null,"abstract":"In the present work, we propose a three-dimensional model of the typical fuel assembly of the AP1000 reactor with the change from conventional fuel to (U, Th)O2. Owing to the complexity of the real model, we made some simplifications to reduce the computational cost and optimise the calculation time. The absence of spacer grids, burnable poisons, and the simulation of only 1/8 of the fuel assembly, culminated in a simplified model, and at the same time, capable of representing the reactor's operating situation under normal conditions. We obtained the power density distribution in the fuel assembly through a neutronic-thermohydraulic coupling, using MCNP6 and ANSYS CFX-19, respectively. One of the main differentials of this model is the consideration of the temperature dependence of thermophysical properties, which shows a direct influence on the results. We assessed the correlations published in some reports about thermal conductivity, density, and specific heat to obtain expressions for these parameters. We determined the temperature profiles, the axial distribution of the coolant density, and the pressure drop in the fuel assembly to assess the thermohydraulic limits. The proposed model presented results according to the project limits for the normal operating conditions of the reactor. The implementation of a robust model provided consistent results, in addition to a methodology capable of carrying out more complex analyses.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"14 1","pages":"97"},"PeriodicalIF":0.0000,"publicationDate":"2020-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Thermohydraulic evaluation of a MOX (U, Th)O2 fuel application in an AP1000 reactor typical fuel assembly\",\"authors\":\"Caio J.C.M.R. Cunha, F. A. Lima, D. Rodríguez\",\"doi\":\"10.1504/ijnest.2020.10034460\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"In the present work, we propose a three-dimensional model of the typical fuel assembly of the AP1000 reactor with the change from conventional fuel to (U, Th)O2. Owing to the complexity of the real model, we made some simplifications to reduce the computational cost and optimise the calculation time. The absence of spacer grids, burnable poisons, and the simulation of only 1/8 of the fuel assembly, culminated in a simplified model, and at the same time, capable of representing the reactor's operating situation under normal conditions. We obtained the power density distribution in the fuel assembly through a neutronic-thermohydraulic coupling, using MCNP6 and ANSYS CFX-19, respectively. One of the main differentials of this model is the consideration of the temperature dependence of thermophysical properties, which shows a direct influence on the results. We assessed the correlations published in some reports about thermal conductivity, density, and specific heat to obtain expressions for these parameters. We determined the temperature profiles, the axial distribution of the coolant density, and the pressure drop in the fuel assembly to assess the thermohydraulic limits. The proposed model presented results according to the project limits for the normal operating conditions of the reactor. The implementation of a robust model provided consistent results, in addition to a methodology capable of carrying out more complex analyses.\",\"PeriodicalId\":35144,\"journal\":{\"name\":\"International Journal of Nuclear Energy Science and Technology\",\"volume\":\"14 1\",\"pages\":\"97\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2020-12-21\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"International Journal of Nuclear Energy Science and Technology\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1504/ijnest.2020.10034460\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"Energy\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"International Journal of Nuclear Energy Science and Technology","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1504/ijnest.2020.10034460","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"Energy","Score":null,"Total":0}
Thermohydraulic evaluation of a MOX (U, Th)O2 fuel application in an AP1000 reactor typical fuel assembly
In the present work, we propose a three-dimensional model of the typical fuel assembly of the AP1000 reactor with the change from conventional fuel to (U, Th)O2. Owing to the complexity of the real model, we made some simplifications to reduce the computational cost and optimise the calculation time. The absence of spacer grids, burnable poisons, and the simulation of only 1/8 of the fuel assembly, culminated in a simplified model, and at the same time, capable of representing the reactor's operating situation under normal conditions. We obtained the power density distribution in the fuel assembly through a neutronic-thermohydraulic coupling, using MCNP6 and ANSYS CFX-19, respectively. One of the main differentials of this model is the consideration of the temperature dependence of thermophysical properties, which shows a direct influence on the results. We assessed the correlations published in some reports about thermal conductivity, density, and specific heat to obtain expressions for these parameters. We determined the temperature profiles, the axial distribution of the coolant density, and the pressure drop in the fuel assembly to assess the thermohydraulic limits. The proposed model presented results according to the project limits for the normal operating conditions of the reactor. The implementation of a robust model provided consistent results, in addition to a methodology capable of carrying out more complex analyses.
期刊介绍:
Today, nuclear reactors generate nearly one quarter of the electricity in nations representing two thirds of humanity, and other nuclear applications are integral to many aspects of the world economy. Nuclear fission remains an important option for meeting energy requirements and maintaining a balanced worldwide energy policy; with major countries expanding nuclear energy"s role and new countries poised to introduce it, the key issue is not whether the use of nuclear technology will grow worldwide, even if public opinion concerning safety, the economics of nuclear power, and waste disposal issues adversely affect the general acceptance of nuclear power, but whether it will grow fast enough to make a decisive contribution to the global imperative of sustainable development.