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Core design of PWR-type seed-blanket core breeder reactor with tightly packed fuel assembly

机译:紧密堆装燃料的压水堆型种子毯芯增殖反应堆堆芯设计

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Pressurized water reactor (PWR) is the reactor type with the most abundant operation experience in the world. However, studies on designing PWR-type fast reactors have been limited and there have not been any PWR-type fast breeder reactor design concepts. In this study, the concept of seed-blanket PWR-type breeder reactor with tightly packed fuel assembly (TPFA) has been developed by coupled three dimensional neutronics and thermal-hydraulics core calculations. For the seed-blanket heterogeneous core using mixed oxide (MOX) fuel and depleted uranium, it has been shown that the core height is limited to about 1.0 m or less, in order to satisfy the design criterion of negative void reactivity. Moreover, it has been shown that increasing the core power density is difficult, as it leads to substantial increase in the core pressure drop. Consequently, the core characteristics are featured by low breeding performance with compound system doubling time (CSDT) of about 150 years or more (fissile plutonium surviving ratio of below 1.01) and low thermal power of about 700 MW or less. For the core using 4.95 wt% enriched uranium for the blanket assembly, it is possible to improve the void reactivity characteristics, breeding performance and thermal power by reducing reactivity difference between the seed and the blanket fuel assemblies. By utilizing enriched uranium, the concept of breeding PWR core with CSDT of 60 years and thermal power of 1000 MW has been shown. In addition, PWR-type breeder reactor concept using enriched uranium that the fissile surviving ratio including uranium and plutonium exceeds 1 was shown for the first time.
机译:压水堆(PWR)是世界上拥有最丰富运行经验的反应堆类型。但是,关于设计PWR型快速反应堆的研究受到限制,并且没有任何PWR型快速增殖反应堆的设计概念。在这项研究中,通过结合三维中子学和热工液压堆芯计算,开发了具有紧密包装燃料组件(TPFA)的种子毯式PWR型增殖反应堆的概念。对于使用混合氧化物(MOX)燃料和贫铀的种子毯型异质核,已经证明,为了满足负空穴反应性的设计标准,核的高度限制为约1.0 m或更小。而且,已经显示出增加芯功率密度是困难的,因为这导致芯压降的显着增加。因此,核心特性的特点是育种性能低,复合系统倍增时间(CSDT)约为150年或更长(易裂p存活率低于1.01)和低热功率约700 MW或更小。对于使用4.95 wt%浓缩铀进行覆盖组件的堆芯,可以通过减少种子和覆盖燃料组件之间的反应性差异来改善空隙反应性,繁殖性能和热功率。通过利用浓缩铀,已经证明了使用60年的CSDT和1000 MW的热功率繁殖PWR堆芯的概念。另外,首次展示了使用富铀的PWR型增殖反应堆概念,其中铀和p的裂变存活率超过1。

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