对一个空的37单元candu®燃料束进行有限元分析,研究压力管蠕变的影响

IF 0.6 CNL Nuclear Review Pub Date : 2021-01-01 DOI:10.12943/cnr.2020.00003
Kyuhwan Lee, D. Wowk, P. Chan
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引用次数: 0

摘要

随着时间的推移,CANDU燃料束会发生塑性变形,蠕变压力管(PT)中燃料束的水平配置会导致冷却剂绕过燃料束下垂的下半部。由于反应器老化,流量有限的管束段可能更容易干燥。使用商业有限元软件ANSYS构建了37元燃料堆的有限元模型,以研究燃料堆的机械变形行为,从而保持可冷却的几何形状。主要关注的是燃料元件之间以及燃料元件与PT之间的接触。由于所有接触对导致模型的复杂性,需要使用高性能计算硬件。证明了附肢之间的接触,并研究了变形对不同边界条件(BC)的敏感性。特别地,元件焊接到端板的径向位置显著影响元件弯曲的幅度。将PT扩展到8%的径向蠕变表明,垫片(SP)和轴承垫片在防止中平面护套与护套接触和护套与PT接触方面具有正确的功能。然而,由于缺乏防止元件过度弯曲的SP,四分之一平面被认为是关键区域。这项工作成功地说明了具有接触的CANDU燃料束的变形,以及与辐照后检查结果和燃料束加热试验相比,其与弓形轮廓的相似性。
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FINITE ELEMENT ANALYSIS OF AN EMPTY 37-ELEMENT CANDU® FUEL BUNDLE TO STUDY THE EFFECTS OF PRESSURE TUBE CREEP
CANDU fuel bundles experience plastic deformations over time, and the horizontal configuration of the bundle in a crept pressure tube (PT) causes coolant to bypass the sagged lower half of the bundle. Bundle segments where the flow is limited may become more susceptible to dryout due to reactor aging. A finite element model of a 37-element fuel bundle was constructed using the commercial finite element software ANSYS to study the mechanical deformation behaviour of the bundle to maintain a coolable geometry. The main focus was on the contact between the fuel elements and between the fuel elements and PT. The complexity of the model due to all the contact pairs necessitated the use of high-powered computing hardware. Contact was demonstrated between the appendages, and sensitivity of the deformation to different boundary conditions (BC) was investigated. In particular, the radial position where the elements were welded to the endplate significantly impacted the magnitude of the element bowing. Expanding the PT up to 8% diametral creep demonstrated the proper functioning of the spacer pads (SP) and bearing pads in preventing sheath-to-sheath contact at the midplane and sheath-to-PT contact. However, the quarter plane was deemed to be the critical region due to the lack of SPs preventing excessive element bowing. This work has successfully illustrated the deformation of a CANDU fuel bundle, with contact, and its similarity with the bow profiles when compared with post-irradiation examination results and bundle heat-up tests.
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CNL Nuclear Review
CNL Nuclear Review NUCLEAR SCIENCE & TECHNOLOGY-
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