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Thermo-mechanical analyses and assessment with respect to the design codes and standards of the HCPB-TBM Breeder Unit

机译:根据HCPB-TBM育种单位的设计规范和标准进行热机械分析和评估

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摘要

The Helium Cooled Pebble Bed-Test Blanket Module (HCPB-TBM) is one of the two breeding blanket concepts currently under development in Europe. Key component of the HCPB-TBM, the Breeder Unit (BU), has entered the detailed engineering design phase. After establishing a base design, thermal and thermo-mechanical analyses have been performed under typical ITER operational conditions: the results are presented and discussed in this paper. A full scaled finite element model of the base design of the HCPB-TBM BU has been built to run thermal analyses of the beryllium and Li_4SO_4 pebble beds and thermo-mechanical analyses of the BU structure, both in steady state and in a typical transient regime during a pulse of the ITER D-T phase. The temperatures reached in the Li_4SO_4 and beryllium pebble beds in the BU base design are 930.8 ℃ and 712.9 ℃, respectively, which are above the recommended values of 920℃ for Li_4SO_4 and 650℃ for the beryllium pebbles. The maximum temperature in the structural steel is 548.4 ℃, which remains under the design limit defined for the TBM studies (550 ℃). In order to decrease the temperature in the hot spots identified in the pebble beds, a reduction of the Li_4SO_4 and beryllium bed volumes has been adopted. As for the structural material, the thermo-mechanical analyses have been assessed with respect the RCC-MR design code (completed for irradiation damages with ITER SDC-IC). The results reveal some problematic points in the base design, concentrated in the coolant inlet and outlet pipes and in the connection region of the BU cooling plates with the BU backplate. Submodeling technique has been used to improve the design in these regions. An increase in the thickness of the coolant inlet and outlet pipes and a redesign of the BU backplate have led to a fulfillment of the codes and standards. The design modifications of pebble bed region and structural material have been implemented in the final design of the BU that is presently used as reference for the design and test of a BU mockup in KIT.
机译:氦气冷却卵石床试验毯模块(HCPB-TBM)是目前欧洲正在开发的两个繁殖毯概念之一。 HCPB-TBM的关键组件育种单元(BU)已进入详细的工程设计阶段。建立基本设计后,已在典型的ITER操作条件下进行了热力和热力分析:在本文中介绍和讨论了结果。已建立了HCPB-TBM BU基础设计的全尺寸有限元模型,以在稳态和典型瞬态下运行铍和Li_4SO_4卵石床的热分析以及BU结构的热机械分析在ITER DT阶段的脉冲期间。在BU基础设计中,Li_4SO_4和铍卵石床所达到的温度分别为930.8℃和712.9℃,高于Li_4SO_4和铍卵石的建议温度920℃。结构钢的最高温度为548.4℃,仍低于TBM研究规定的设计极限(550℃)。为了降低卵石床中发现的热点温度,已采用减少Li_4SO_4和铍床体积的方法。对于结构材料,已经根据RCC-MR设计规范(针对ITER SDC-IC的辐照损伤完成)对热机械分析进行了评估。结果表明,在基础设计中存在一些问题点,这些问题集中在冷却剂入口和出口管以及BU冷却板与BU背板的连接区域中。子建模技术已用于改善这些区域的设计。冷却液入口和出口管厚度的增加以及BU背板的重新设计导致满足规范和标准。卵石床区域和结构材料的设计修改已在BU的最终设计中进行,目前已作为KIT中BU模型的设计和测试的参考。

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