原子能科学技术
原子能科學技術
원자능과학기술
ATOMIC ENERGY SCIENCE AND TECHNOLOGY
2015年
1期
58-63
,共6页
郭超%温丽晶%刘宇生%张盼%马帅
郭超%溫麗晶%劉宇生%張盼%馬帥
곽초%온려정%류우생%장반%마수
瞬态工况%稳压器波动管%热分层%数值模拟
瞬態工況%穩壓器波動管%熱分層%數值模擬
순태공황%은압기파동관%열분층%수치모의
transient condition%pressurizer surge line%thermal stratification%numerical simulation
利用计算流体动力学软件ANSYS/CFX ,对秦山核电二期扩建工程2×650 MW压水堆核电站四号机组核岛厂房的稳压器波动管进行了三维全尺寸非稳态计算。建立了波动管整体和不同截面的热分层瞬态,对管内热分层流动与换热进行了研究。研究结果表明:同一截面内高温层流体和低温层流体的升温方式不同;不同截面位置的管内流动温度分布特性差别较大,但均呈现分层流体温差先增大后减小的趋势。计算结果可为后续波动管热应力分析及寿命评价提供一定基础。
利用計算流體動力學軟件ANSYS/CFX ,對秦山覈電二期擴建工程2×650 MW壓水堆覈電站四號機組覈島廠房的穩壓器波動管進行瞭三維全呎吋非穩態計算。建立瞭波動管整體和不同截麵的熱分層瞬態,對管內熱分層流動與換熱進行瞭研究。研究結果錶明:同一截麵內高溫層流體和低溫層流體的升溫方式不同;不同截麵位置的管內流動溫度分佈特性差彆較大,但均呈現分層流體溫差先增大後減小的趨勢。計算結果可為後續波動管熱應力分析及壽命評價提供一定基礎。
이용계산류체동역학연건ANSYS/CFX ,대진산핵전이기확건공정2×650 MW압수퇴핵전참사호궤조핵도엄방적은압기파동관진행료삼유전척촌비은태계산。건립료파동관정체화불동절면적열분층순태,대관내열분층류동여환열진행료연구。연구결과표명:동일절면내고온층류체화저온층류체적승온방식불동;불동절면위치적관내류동온도분포특성차별교대,단균정현분층류체온차선증대후감소적추세。계산결과가위후속파동관열응력분석급수명평개제공일정기출。
T he thermal stratification under transient condition in pressurizer surge line of Qinshan Phase Ⅱ extension nuclear power project (2 × 650 MW PWR generator 4) was investigated by computational fluid dynamics program ANSYS/CFX .The whole and cross‐sectional thermal stratification transient analysis models for the pressurizer surge line were established ,and the heat stratified flow and heat transfer of the surge line were studied .The way of temperature growth is different between high‐and low‐temperature fluid layers in the same cross section . T he fluid temperature distribution has great difference in different cross sections , but the temperature difference first increases and then decreases in every cross section .The research results can provide a basis for subsequent analysis of thermal stress and lifespan .