CAJ | 학술논문

为探讨不同淬火温度对核燃料包壳管Zr-4合金力学性能的影响．本文分析了Zr-4合金的显微组织，通过对再结晶退火态的Zr-4合金进行不同温度淬火及回火热处理，在不同热处理状态下对试样进行室温环向拉伸试验，分析对比了试样的拉伸力学性能，并对拉伸后的试样进行断口扫描，分析断裂机理．试验结果表明：包壳管Zr-4合金在980℃淬火后晶粒弦长为145．62μm ，相比920℃、950℃的弦长增大，其抗拉强度为740 M Pa ，屈服强度为649 M Pa ．淬火后断口类型属解理脆性断裂．
위탐토불동쉬화온도대핵연료포각관Zr-4합금역학성능적영향．본문분석료Zr-4합금적현미조직，통과대재결정퇴화태적Zr-4합금진행불동온도쉬화급회화열처리，재불동열처리상태하대시양진행실온배향랍신시험，분석대비료시양적랍신역학성능，병대랍신후적시양진행단구소묘，분석단렬궤리．시험결과표명：포각관Zr-4합금재980℃쉬화후정립현장위145．62μm ，상비920℃、950℃적현장증대，기항랍강도위740 M Pa ，굴복강도위649 M Pa ．쉬화후단구류형속해리취성단렬．
The microstructures and properties of Zr-4 alloy after heat-treatment in different quenching temperatures were studied .The tensile properties of tubes of different heat-treatment were studied by means of static tensile test at room temperature .The fracture mechanisms of Zr-4 tubes after tensile test were studied by SEM .The result showed that the grain chord length after 980 ℃ quenching was 145 .62μm and was longer than that at other temperatures .The tensile strength was 740 MPa ,and the yield strength was 649 MPa after quenching at 980 ℃ .The tensile fracture of Zr-4 alloys occured in the manner of cleavage brittle fracture at room temperature according to the SEM fracture surface observation .