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首页> 外文期刊>Journal of nuclear engineering and radiation science >A Thoria and Thorium Uranium Dioxide Nuclear Fuel Performance Model Prototype and Knowledge Gap Assessment
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A Thoria and Thorium Uranium Dioxide Nuclear Fuel Performance Model Prototype and Knowledge Gap Assessment

机译：二氧化钍和二氧化钍核燃料效果模型原型和知识差距评估

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摘要

Thorium-based fuel cycles can improve fuel sustainability within the nuclear power industry. The Canadian supercritical water-cooled reactor (SCWR) concept uses this path to achieve the sustainability requirement of the Gen-IV Forum. The study of thorium dioxide/thoria ThO _( 2 ) -based fuel irradiation behavior is significantly less advanced than that of uranium dioxide (UO _( 2 ) ) fuel, although ThO _( 2 ) possesses superior thermal conductivity, thermal expansion, higher melting temperature, and oxidation resistance that may improve both fuel performance and safety. The fuel and sheath modeling tool (FAST), a fuel performance model for UO _( 2 ) fuel, was developed at the Royal Military College of Canada (RMCC). FAST capability has been extended to include thoria (ThO _( 2 ) ), thorium uranium dioxide (Th,U)O _( 2 ) , and thorium plutonium dioxide (Th,Pu)O _( 2 ) as fuel pellet materials, to aid in designing and performance assessment of Th-based fuels, including SCWR (Th,Pu)O _( 2 ) fuel. The development and integration of ThO _( 2 ) and (Th,U)O _( 2 ) models into the existing FAST model led to the multipellet material FAST (MPM-FAST). Model development was performed in collaboration between RMCC and Canadian Nuclear Laboratories (CNL). This paper presents an outline of the ThO _( 2 ) and (Th,U)O _( 2 ) MPM-FAST model, a comparison between modeling results with postirradiation examination (PIE) data from a test conducted at CNL, and an account of the knowledge gap between our ability to model ThO _( 2 ) and (Th,U)O _( 2 ) fuel compared to UO _( 2 ) . Results are encouraging when compared to PIE data.
机译：钍基燃料循环可以提高核电工业内的燃料可持续性。加拿大超临界水冷反应堆（SCWR）概念使用该路径来实现Gen-IV论坛的可持续性要求。基于二氧化钍/钍的研究比二氧化碳的燃料辐照行为显着不如二氧化铀（UO _（2））燃料，尽管_（2）具有卓越的导热系数，热膨胀，更高熔化温度和抗氧化性可能改善燃料性能和安全性。燃料和护套建模工具（FAST）是UO _（2）燃料的燃料性能模型，是在加拿大皇家军事学院（RMCC）开发的。快速的能力已经扩展到包括梭罗（Tho _（2）），二氧化钍（Th，U）O _（2）和二氧化钍（Th，PU）O _（2）作为燃料颗粒材料，至于燃料颗粒材料帮助设计和性能评估基于Th的燃料，包括SCWR（TH，PU）O _（2）燃料。 Tho _（2）和（Th，U）O _（2）模型进入现有快速模型的开发和集成，以快速（MPM-FAST）LED为多芯片材料。在RMCC和加拿大核实验室（CNL）之间的合作进行了模型开发。本文介绍了THO _（2）和（TH，U）O _（2）MPM-FAST模型的轮廓，在CNL的测试中与PostImariation检查（PIE）数据的建模结果的比较，以及一个账户与UO _（2）相比，我们模拟Tho（2）和（2）和（2）_（2）燃料的能力之间的知识差距。与饼数据相比，结果令人鼓舞。

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