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首页> 外文期刊>Progress in Nuclear Energy >Neutronic and thermal-hydraulic analysis of alternative ceramic fuels in the next-generation of light water reactors
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Neutronic and thermal-hydraulic analysis of alternative ceramic fuels in the next-generation of light water reactors

机译：下一代轻水反应堆中替代陶瓷燃料的中子学和热工水力分析

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The Burn-Up enlargement is one of the most important issues in the nuclear reactor core fuel management. In recent years some reactor design companies have focused on the reactor cycle length enlargement in next generation of pressurized water reactors. An increased cycle length results in an increased fuel burn-up which directly leads to low electricity costs and more efficiency. One of the promising issues is to change the chemical state of fuel that is on the agenda of the Mitsubishi Company as US-APWR nuclear power plant designer. In the present study, the neutronic as well as thermal hydraulic analysis of some commercial ceramic fuels such as UN, UC, and UN15 instead of conventional UO2 have been studied. The sub-channel analysis approach has been selected for these investigations. In this regard, a US-APWR fuel assembly was modelled using MCNPX2.6 Monte Carlo code by considering the periodic boundary condition in X-Y directions. It was found that the use of UC and UN15 instead of UO2 has a deep effect on the reactor cycle length such that the power plant operational time was increased by a factor of 1.5. The COBRA-EN code with modified MATPRO subroutine has been used in thermal-hydraulic tasks. Since the thermal conductivity of these selected fuels is six times greater than UO2, the thermal-hydraulic analysis of candidate fuels was led to outstanding results. It was found that the fuel centerline temperature in UN15 and UC cases are about half of UO2 one, which is drastically beneficial. In summary the thermal power of next generation of pressurized water reactors could be increased considerably by using the candidate ceramic fuels instead of conventional UO2 one. (C) 2015 Elsevier Ltd. All rights reserved.
机译：燃尽放大是核反应堆堆芯燃料管理中最重要的问题之一。近年来，一些反应堆设计公司将重点放在下一代压水反应堆的反应堆循环长度增加上。增加的循环长度导致增加的燃料消耗，这直接导致较低的电力成本和更高的效率。有希望的问题之一是改变三菱公司作为美国-APWR核电站设计者的议事日程的燃料化学状态。在本研究中，已经研究了一些商用陶瓷燃料（例如UN，UC和UN15）而不是常规UO2的中子学分析和热工水力分析。已为这些调查选择了子渠道分析方法。在这方面，通过考虑X-Y方向上的周期性边界条件，使用MCNPX2.6蒙特卡洛代码对US-APWR燃料组件进行了建模。发现使用UC和UN15代替UO2对反应堆循环长度有深远的影响，因此电厂的运行时间增加了1.5倍。带有修改过的MATPRO子例程的COBRA-EN代码已用于热工液压任务。由于这些选定燃料的热导率是UO2的六倍，因此对候选燃料进行热工水力分析得到了出色的结果。发现在UN15和UC情况下，燃料中心线温度约为UO2的一半，这是非常有利的。总之，通过使用候选陶瓷燃料代替常规的UO2，可以大大提高下一代压水堆的热功率。 （C）2015 Elsevier Ltd.保留所有权利。

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