核动力工程
覈動力工程
핵동력공정
NUCLEAR POWER ENGINEERING
2010年
1期
4-8
,共5页
核反应堆%压力容器钢%富Cu原子团簇%辐照脆化%力学性能%三维原子探针
覈反應堆%壓力容器鋼%富Cu原子糰簇%輻照脆化%力學性能%三維原子探針
핵반응퇴%압력용기강%부Cu원자단족%복조취화%역학성능%삼유원자탐침
Nuclear reactor%RPV steel%Copper-enriched clusters%Radiation embrittlement%Mechanical properties%3DAP
采用淬火和时效处理方法诱发压力容器模拟钢中的微量杂质元素Cu以富铜原子团簇析出.力学性能试验结果表明,富铜原子团簇的出现导致压力容器模拟钢韧脆转变温度出现明显变化,而屈服强度和抗拉强度增长较小,塑性也只有较小程度下降.三维原子探针分析结果表明,富铜原子团簇的数密度为10~(23) m~(-3)数量级,富铜原子团簇直径为1～3 nm.
採用淬火和時效處理方法誘髮壓力容器模擬鋼中的微量雜質元素Cu以富銅原子糰簇析齣.力學性能試驗結果錶明,富銅原子糰簇的齣現導緻壓力容器模擬鋼韌脆轉變溫度齣現明顯變化,而屈服彊度和抗拉彊度增長較小,塑性也隻有較小程度下降.三維原子探針分析結果錶明,富銅原子糰簇的數密度為10~(23) m~(-3)數量級,富銅原子糰簇直徑為1～3 nm.
채용쉬화화시효처리방법유발압력용기모의강중적미량잡질원소Cu이부동원자단족석출.역학성능시험결과표명,부동원자단족적출현도치압력용기모의강인취전변온도출현명현변화,이굴복강도화항랍강도증장교소,소성야지유교소정도하강.삼유원자탐침분석결과표명,부동원자단족적수밀도위10~(23) m~(-3)수량급,부동원자단족직경위1～3 nm.
The precipitation of copper-enriched clusters was induced into pressure vessel model steel (with higher Cu content) of nuclear reactors by water quenching and thermal aging. The mechanical property tests showed that the presence of copper-enriched clusters led to a large shift of the ductile-to-brittle transition temperature, a tiny increase in the yield strength and tensile strength, and a tiny decrease of plasticity. In addi-tion, this paper also studied the effect of the presence of Nickel element on the ductile-to-brittle transition temperature. Three-dimensional atom probe test revealed that the number density of enriched clusters was about 10~(23) m~(-3), and the size of copper-enriched clusters was in the range of 1nm to 3nm in diameter.
