秦山核电厂压水堆考验燃料组件辐照后检验  

A POST-IRRADIATION EXAMINATION FOR TESTING FUEL ASSEMBLY OF QINSHAN PWR

作　　者：王树人[1] 韩传斌[1] 潘旦光[1] 李秀茗 梁启东[1] 杨忠科 黄清良[1] 田克昌 

机构地区：[1]中国原子能科学研究院

出　　处：《核科学与工程》1994年第3期235-242,共8页Nuclear Science and Engineering

摘　　要：为验证秦山核电厂压水型反应堆燃料组件的设计、制造工艺和材料性能，采用３×３考验组件，在原子能院重水试验堆ＨＷＲＲ的高温高压回路中模拟秦山核电厂反应堆的稳态和短时超功率工况进行了综合考验，平均燃耗达２５７００ＭＷｄ／ｔＵ。对考验组件和燃料棒作了综合性的辐照后检验，检验项目包括：燃料棒的外观观察、尺寸测量、γ扫描、涡流探伤、Ｘ射线照相、裂变气体释放率测量，包壳管、控制棒导向管和格架弹簧片的力学性能试验，包壳和燃料芯块的微观组织分析和定量测量，水垢的Ｘ射线衍射分析等。检验结果表明：考验组件设计合理，制造工艺可靠，燃料芯块、包壳和其它材料的性能均能满足要求。所取得的检验结果可为秦山核电厂压水堆的燃料组件以及同类燃料组件的设计、制造和性能改进提供依据。The short test fuel assembly(3 ×3) for Qinshan PWR was irradiated up to burnup 25700MWd/tU in the in-pile loop( 15. 5 MPa, 320℃ ) at HWRR, CIAE, at simulative condition to Qinshan PWR normal and shortrun overpower operation for verifying the design.technology and material properties of fuel assembly. Comprehensive post-irradiation examinations(PIE) including visual inspection. dimension measurement、 gamma scanning.eddy current crack detection、X -ray radiography.measurement of fission gas release、 tensile test、 quantitative metallography and ceramography etc. were performed. PIE results show that the design of test assembly is reasonable, the technology is reliable and the properties of pellets. cladding and other materials are satisfied. The results would be an important basis for further improvement of design. technology and material properties for Qinshan PWR assembly.

关 键 词：燃料组件 辐照后检验 核电厂 压水反应堆 

分 类 号：TL421.105[核科学技术—核技术及应用]