S271钢的中子辐照实验  

NEUTRON IRRADIATION TEST OF THE S271 STEEL

作　　者：高维森[1] 杨明金[1] 

机构地区：[1]中国核动力研究设计院

出　　处：《中国核科技报告》1991年第S3期23-23,共1页China Nuclear Science and Technology Report

摘　　要：将上海重型机器厂的S271钢在HFETR上进行了辐照考验。用冲击韧性和室温拉伸性能对其中子辐照脆性作了检验,确定了它们的转变温度的升高和上平台能量(USE)的降低。结果表明:在288℃,～3×10^(19)n/cm^2辐照后,T×T/4试样的脆性转变温度的增值仅为41～43℃;从给水管套料的辐照脆化看,则是纵向小于切向;三种试样的USE都大于160J。The irradiation test of the S271 produced by the Heavy Machinery Plant in Shanghai has been tested in the High Flux Engineering Test Reactor (HFETR) . The neutron irradiation brittleness of the steel was examined by Charpy impact toughness test and room temperature tensile test, the transition temperature in-crese and upper shelf energy (USE) decrease were determined. The test results showed that after 3X 1019n/cm2 neutron irradiated at 288 C, the increase of brittleness transition temperature for TXT/4 samples was 41-43C. The irradiation brittleness for the tube material of water supply pipe in the longitudinal direction is smaller than in the tangential direction. The USE of all three samples are greater than 160.

关 键 词：中子辐照 动力研究 HFETR 辐照脆化 辐照考验 设计院 室温拉伸性能 套料 上平台 明金 

分 类 号：TL[核科学技术]