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首页> 外文期刊>Journal of nuclear engineering and radiation science >Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water
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Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water

机译:通过超临界压力轻水冷却的高育种快速反应器的核心设计

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摘要

The authors look for an attractive light water reactor (LWR) concept, which achieves high breeding performance with respect to the compound system doubling time (CSDT). In the preceding study, a high breeding fast reactor concept, cooled by supercritical pressure light water (Super FBR), was developed using tightly packed fuel assembly (TPFA) concept, in which fuel rods were arranged in a hexagonal lattice and packed by contacting each other. However, the designed concept had characteristics, which had to be improved, such as low power density (7.4?kW/m), large core pressure loss (1.02?MPa), low discharge burnup (core average: 8 GWd/t), and low coolant temperature rise in the core (38?°C). The aim of this study is to clarify the main issues associated with improvement of the Super FBR with respect to these design parameters and to show the improved design. The core design is carried out by fully coupled three-dimensional neutronics and single-channel thermal-hydraulic core calculations. The design criteria are negative void reactivity, maximum linear heat generation rate (MLHGR) of 39?kW/m, and maximum cladding surface temperature (MCST) of 650?°C for advanced stainless steel. The results show that significant improvement is possible with respect to the core thermal-hydraulic characteristics with minimal deterioration of CSDT by replacing TPFA with the commonly acknowledged hexagonal tight lattice fuel assembly (TLFA). Further design studies are necessary to improve the core enthalpy rise by reducing the radial power swing and power peaking.
机译:作者寻找一个有吸引力的轻型水反应堆(LWR)概念,这对化合物系统倍增时间(CSDT)实现了高育种性能。在前述研究中,使用紧密填充的燃料组件(TPFA)概念开发了一种高育种快速反应器概念,由超临界压力轻质水(超级FBR)开发,其中燃料棒布置在六边形晶格中并通过接触填充其他。然而,设计的概念具有特性,必须改善,例如低功率密度(7.4 kW / m),大核心压力损失(1.02?mpa),低放电燃烧(核心平均:8 gwd / t),核心(38Ω°C)中的低冷却剂温度升高。本研究的目的是阐明与这些设计参数的超级FBR改进相关的主要问题,并显示改进的设计。核心设计通过完全耦合的三维中型和单通道热液压芯计算来执行。设计标准是负空隙反应性,39 kW / m的最大线性发热速率(MLHGR),以及650°C的最大包层表面温度(MCST),用于先进的不锈钢。结果表明,通过用通常确认的六边形紧密晶格燃料组件(TLFA)通过更换TPFA,可以对核心热液压特性具有显着改进,通过替换TPFA,通过替换TPFA,通过替换TPFA。通过减少径向动力摆动和功率峰值,需要进一步设计研究来提高核心焓升高。

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