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Thermal Feasibility Analyses for the 135GMWe High Conversion-Type Innovative Water Reactor for Flexible Fuel Cycle

机译:用于柔性燃料循环的135GMWe高转化率创新型水反应堆的热可行性分析

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A new reactor concept of innovative water reactor for flexible fuel cycle (FLWR) is under development at Japan Atomic Energy Agency in cooperation with Japanese reactor suppliers. A design of 1,356 MWe high conversion boiling water reactor-type FLWR core, which has an instantaneous conversion ratio of 1.04, negative void coefficient, high burnup of 65 GWd/t, and 15-month operational cycle length, has been constructed. So far, studies on thermal-hydraulic characteristics have been performed for tight lattice core. Evaluation methods for the critical power and the pressure drop under both the steady and the transient states have been established, and a modified TRAC-BF1 code has been developed for the thermal-hydraulic design of the FLWR. In this paper, the thermal feasibility of the designed 1356MWe FLWR core is analyzed by using the modified TRAC-BF1 code. The analysis is first carried out for the current core design. It is confirmed that no boiling transition (BT) occurs under the steady state. However, the minimum critical power ratio (MCPR) is only about 1.08, and the BT is confirmed occurring under the postulated abnormal transient processes. Therefore, concretizations of the conditions that ensure the thermal feasibility of a natural circulation-type FLWR and a forced circulation-type FLWR are performed. As for the results, for a forced circulation-type FLWR, the operation-limited MCPR (OLMCPR) is 1.32, and the necessary minimum core coolant flow rate is 640 kg/(m~2s). For a natural circulation-type FLWR, the OLMCPR is 1.19, and the necessary minimum core coolant flow rate is 560 kg/(m~2s).
机译:日本原子能机构与日本反应堆供应商合作,正在开发一种用于灵活燃料循环(FLWR)的创新水反应堆的新反应堆概念。设计了一个1,356 MWe高转化率沸水反应堆型FLWR堆芯,其瞬时转化率为1.04,负孔隙系数,65 GWd / t的高燃耗率和15个月的运行周期长度。到目前为止,已经对致密晶格芯进行了热工水力特性的研究。建立了稳态和瞬态状态下的临界功率和压降的评估方法,并为FLWR的热工设计开发了改进的TRAC-BF1代码。本文使用改进的TRAC-BF1代码分析了设计的1356MWe FLWR铁芯的热可行性。首先对当前的核心设计进行分析。可以确定在稳态下没有发生沸腾转变(BT)。但是,最小临界功率比(MCPR)仅约为1.08,并且可以确定在假定的异常瞬态过程下发生了BT。因此,进行确保自然循环式FLWR和强制循环式FLWR的热可行性的条件的具体化。结果表明,对于强制循环式FLWR,运行极限MCPR(OLMCPR)为1.32,必要的最小堆芯冷却液流速为640 kg /(m〜2s)。对于自然循环型FLWR,OLMCPR为1.19,必要的最小堆芯冷却液流速为560 kg /(m〜2s)。

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