核动力工程
覈動力工程
핵동력공정
NUCLEAR POWER ENGINEERING
2010年
1期
9-12
,共4页
薛飞%束国刚%遆文新%余伟炜%蒙新明%刘江南%石崇哲
薛飛%束國剛%遆文新%餘偉煒%矇新明%劉江南%石崇哲
설비%속국강%제문신%여위위%몽신명%류강남%석숭철
核电厂%热老化%铸造不锈钢%冲击性能%预测
覈電廠%熱老化%鑄造不鏽鋼%遲擊性能%預測
핵전엄%열노화%주조불수강%충격성능%예측
Nuclear power plant%Thermal aging%Casting stainless steel%Impact property%Prediction
采用GB/T19748-2005钢材夏比V型缺口摆锤冲击试验仪器化试验方法,对压水堆核电厂用离心铸造Z3CN20.09M奥氏体不锈钢主管道样品进行了实验室热老化的冲击性能研究.冲击试验数据的统计分析表明,热老化对F_(iu)/F_m比值不产生影响,而对冲击载荷有显著影响,对冲击能量的影响则更为显著.透射电子显微分析表明,热老化导致铁素体中出现沉淀物,并引发了奥氏体中位错组态的改变.与热老化时间lg t之间也满足线性关系.
採用GB/T19748-2005鋼材夏比V型缺口襬錘遲擊試驗儀器化試驗方法,對壓水堆覈電廠用離心鑄造Z3CN20.09M奧氏體不鏽鋼主管道樣品進行瞭實驗室熱老化的遲擊性能研究.遲擊試驗數據的統計分析錶明,熱老化對F_(iu)/F_m比值不產生影響,而對遲擊載荷有顯著影響,對遲擊能量的影響則更為顯著.透射電子顯微分析錶明,熱老化導緻鐵素體中齣現沉澱物,併引髮瞭奧氏體中位錯組態的改變.與熱老化時間lg t之間也滿足線性關繫.
채용GB/T19748-2005강재하비V형결구파추충격시험의기화시험방법,대압수퇴핵전엄용리심주조Z3CN20.09M오씨체불수강주관도양품진행료실험실열노화적충격성능연구.충격시험수거적통계분석표명,열노화대F_(iu)/F_m비치불산생영향,이대충격재하유현저영향,대충격능량적영향칙경위현저.투사전자현미분석표명,열노화도치철소체중출현침정물,병인발료오씨체중위착조태적개변.여열노화시간lg t지간야만족선성관계.
The impact property of the centrifugal casting austenite stainless steel Z3CN20.09M manufactured by France was studied with Charpy impact test, which is used as the primary loop pipe in PWR nuclear power plant. Statistical analysis of the instrumental impact test data indicates that thermal ageing has no effect on the ratio value Fu/Fm but a significant influence on the impact force and especially on the impact energy. TEM analysis indicates that the shape of dislocations in austenitic has changed, and precipitations have appeared in ferrite. Extrapolation prediction of the impact property is performed by the regression functions established in this study.