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首页> 外文会议>International conference on the physics of reactors;PHYSOR 2010 >GENERALIZED EQUIVALENCE THEORY FOR CHECKERBOARD CONFIGURATIONS IN NATURAL-URANIUM CANDU LATTICES
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GENERALIZED EQUIVALENCE THEORY FOR CHECKERBOARD CONFIGURATIONS IN NATURAL-URANIUM CANDU LATTICES

机译：天然铀坎杜晶格中棋盘结构的广义等价理论

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CANDU reactors are heavy-water moderated and cooled. They consist of a horizontal, cylindrical, non-pressurized calandria vessel which contains the heavy-water moderator and is penetrated axially by fuel channels. Fuel channels hold the fuel bundles, which are cooled by the flow of coolant at high temperature and pressure. The coolant flows in opposite directions in adjacent channels. For a CANDU 6 reactor, there are 380 fuel channels, each holding 12 37-element fuel bundles, approximately 10-cm in diameter and 50-cm long each. The distance between channels (lattice pitch) is 28.575 cm. CANDU reactors in current operation are fuelled exclusively with natural uranium. Traditionally, neutronics calculations for natural-uranium CANDU lattices use standard homogenization and therefore do not employ discontinuity factors. It is therefore of interest to find out whether gains in accuracy are to be made by adopting Generalized Equivalence Theory (GET) and hence the use of discontinuity factors. Of particular interest are configurations in which neutronic properties of lattice cells alternate in a checkerboard pattern. Such patterns occur in CANDU reactors because of alternating fuelling directions in neighbouring channels and because neighbouring channels belong to different coolant loops or different passes within the same loop. The work presented in this paper assesses the accuracy of the standard homogenization method when applied to checkerboard configurations and investigates whether the use of GET yields more accurate results. The conclusion is that for checkerboard configurations in natural-uranium CANDU lattices use of GET achieves only modest accuracy gains due to the fact that discontinuity factors vary negligibly with local burnup and void conditions.
机译：CANDU反应堆采用重水调节和冷却。它们由水平，圆柱形，无压力的排管容器组成，该容器包含重水减速剂，并被燃料通道轴向穿透。燃料通道容纳燃料束，燃料束在高温和高压下被冷却液流冷却。冷却剂沿相反方向在相邻通道中流动。对于CANDU 6反应堆，有380个燃料通道，每个通道容纳12个37元素的燃料束，直径约10厘米，长50厘米。通道之间的距离（晶格间距）为28.575厘米。当前运行的CANDU反应堆仅使用天然铀作为燃料。传统上，天然铀CANDU晶格的中子学计算使用标准均质化，因此不采用不连续性因子。因此，有兴趣了解是否通过采用广义等效理论（GET）并因此采用不连续性因子来获得准确性的提高。特别令人感兴趣的是其中晶格单元的中子学性质以棋盘图案交替的配置。由于相邻通道中的燃料方向交替变化，并且相邻通道属于不同的冷却剂回路或同一回路内的不同通道，因此在CANDU反应堆中会出现这种模式。本文介绍的工作评估了应用于棋盘格配置的标准均质化方法的准确性，并调查了GET的使用是否产生更准确的结果。结论是，对于自然铀CANDU晶格中的棋盘配置，由于不连续性因素随局部燃耗和空隙条件而变化不大，因此使用GET只能获得适度的精度提高。

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