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Overview and progress in the European project: 'Supercritical Water Reactor - Fuel Qualification Test'

机译:欧洲项目的概述和进展:“超临界水反应堆-燃料鉴定测试”

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The Supercritical Water Reactor (SCWR) is one of the six reactors being investigated under the framework of the Generation Ⅳ International Forum (GIF). One of the major challenges in the development of a SCWR is to develop materials for the fuel and core structures that will be sufficiently corrosion-resistant to withstand supercritical water conditions. Previously, core, reactor and plant design concept of the European High Performance Light Water Reactor (HPLWR) have been worked out in substantial detail. As the next step, it has been proposed to carry out a fuel qualification test of a small scale fuel assembly in a research reactor under typical prototype conditions. Design and licensing of an experimental facility for the fuel qualification test, including the small scale fuel assembly, the required coolant loop with supercritical water and safety and auxiliary systems, is the scope of the project "Supercritical Water Reactor - Fuel Qualification Test" (SCWR-FQT) described here. This project is a collaborative project co-funded by the European Commission, which takes advantage of a Chinese - European collaboration, in which China offers an electrically heated out-of-pile loop for testing of fuel bundles. The results of these out-of-pile tests on an electrically heated, but otherwise identical, fuel assembly shall be used as a pre-qualification experiment as well as for providing data for CFD and system codes validation. A significant part of the design and the necessary structural, CFD, neutronic and safety analyses had been completed. The design of the facility, and especially of the test section with the fuel assembly, as well as the most important results of the above mentioned analyses are presented. Material test results of the stainless steels considered for the fuel cladding are briefly summarized. Finally, important outcomes and lessons learnt in the "Education & Training" and "Management" work packages are presented.
机译:超临界水反应堆(SCWR)是在第四代国际论坛(GIF)框架下正在研究的六个反应堆之一。开发SCWR的主要挑战之一是开发用于燃料和堆芯结构的材料,该材料应具有足够的耐腐蚀性以承受超临界水条件。以前,已经对欧洲高性能轻水反应堆(HPLWR)的堆芯,反应堆和工厂设计概念进行了详尽的阐述。下一步,建议在典型的原型条件下对研究堆中的小型燃料组件进行燃料鉴定测试。 “超临界水反应堆-燃料鉴定测试”(SCWR)项目的范围是为燃料鉴定测试提供实验设施的设计和许可,包括小型燃料组件,所需的冷却剂回路以及超临界水和安全及辅助系统。 -FQT)。该项目是由欧盟委员会共同资助的一项合作项目,该项目利用了中欧合作的优势,在该项目中,中国提供了一个电加热的堆外循环回路,用于测试燃料束。这些在电加热但其他相同的燃料组件上进行的堆外测试的结果应被用作资格预审实验,并为CFD和系统代码验证提供数据。设计的重要部分以及必要的结构,CFD,中子学和安全性分析已经完成。介绍了设备的设计,尤其是带有燃料组件的测试部分的设计,以及上述分析的最重要结果。简要总结了用于燃料包壳的不锈钢的材料测试结果。最后,介绍了在“教育与培训”和“管理”工作包中获得的重要成果和经验教训。

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