首页> 外文会议>International conference on the physics of reactors;PHYSOR 2012 >ASSESSMENT OF POSSIBLE CYCLE LENGTHS FOR FULLY- CERAMIC MICRO-ENCAPSULATED FUEL-BASED LIGHT WATER REACTOR CONCEPTS
【24h】

ASSESSMENT OF POSSIBLE CYCLE LENGTHS FOR FULLY- CERAMIC MICRO-ENCAPSULATED FUEL-BASED LIGHT WATER REACTOR CONCEPTS

机译:完全陶瓷微囊化燃料轻质水反应堆概念可能的循环长度评估

获取原文

摘要

The use of TRISO-particle-based dispersion fuel within SiC matrix and cladding materials has the potential to allow the design of extremely safe LWRs with accident-tolerant fuel. This paper examines the feasibility of LWR-like cycle length for such a low enriched uranium fuel with the imposed constraint of strictly retaining the original geometry of the fuel pins and assemblies. The motivation for retaining the original geometry is to provide the ability to incorporate the fuel "as- is" into existing LWRs while retaining their thermal-hydraulic characteristics. The feasibility of using this fuel is assessed by looking at cycle lengths and fuel failure rates. Other considerations (e.g., safety parameters, etc.) were not considered at this stage of the study. The study includes the examination of different TRISO kernel diameters without changing the coating layer thicknesses. The study shows that a naive use of UO_2 results in cycle lengths too short to be practical for existing LWR designs and operational demands. Increasing fissile inventory within the fuel compacts shows that acceptable cycle lengths can be achieved. In this study, starting with the recognized highest packing fraction practically achievable (44%), higher enrichment, larger fuel kernel sizes, and the use of higher density fuels have been evaluated. The models demonstrate cycle lengths comparable to those of ordinary LWRs. As expected, TRISO particles with extremely large kernels are shown to fail under all considered scenarios. In contrast, the designs that do not depart too drastically from those of the nominal NGNP HTR fuel TRISO particles are shown to perform satisfactorily and display a high rate of survival under all considered scenarios. Finally, it is recognized that relaxing the geometry constraint will result in satisfactory cycle lengths even using UO_2-loaded TRISO particles-based fuel with enrichment at or below 20 w/o.
机译:在SiC基体和覆层材料中使用基于TRISO颗粒的分散燃料有可能允许设计具有事故容忍性燃料的极其安全的轻水堆。本文研究了这样的低浓铀燃料的类似LWR循环长度的可行性,并严格限制了燃料销和组件的原始几何形状。保持原始几何形状的动机是提供将燃料“按原样”并入现有轻水堆的能力,同时保留其热工液压特性。通过查看循环长度和燃料故障率来评估使用这种燃料的可行性。在此研究阶段未考虑其他考虑因素(例如,安全参数等)。该研究包括在不改变涂层厚度的情况下检查不同的TRISO籽粒直径。研究表明,天真地使用UO_2会导致周期长度太短而无法满足现有LWR设计和操作需求。燃料块中易裂变库存的增加表明可以达到可接受的循环长度。在这项研究中,从公认的实际最高填充率(44%)开始,已经评估了更高的浓缩度,更大的燃料核尺寸以及使用了更高密度的燃料。这些模型展示了与普通轻水堆可比的周期长度。不出所料,在所有考虑的情况下,具有巨大内核的TRISO粒子都将失败。相反,在所有考虑到的情况下,与名义NGNP HTR燃料TRISO颗粒的设计都没有太大差异的设计显示出令人满意的性能,并显示出较高的存活率。最后,人们认识到,即使使用浓缩度为20 w / o或低于20 w / o的UO_2负载的TRISO颗粒基燃料,放宽几何形状约束也会产生令人满意的循环长度。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号