原子能科学技术
原子能科學技術
원자능과학기술
ATOMIC ENERGY SCIENCE AND TECHNOLOGY
2015年
8期
1374-1379
,共6页
压水堆%环形燃料%热工水力%最佳排列方式
壓水堆%環形燃料%熱工水力%最佳排列方式
압수퇴%배형연료%열공수력%최가배렬방식
PWR%annular fuel%thermal-hydraulics%the best array
以秦山二期压水堆为参考堆型，对压水堆环形燃料结构进行热工水力分析方法研究。应用SAAF程序分析了从11×11到15×15等5种不同排列方式中不同尺寸的环形燃料棒的热工水力性能，综合最小偏离泡核沸腾比、压降和燃料芯块温度等参数确定了环形燃料组件最佳排列方式为13×13。本文研究结果为相关专业分析提供了初始计算模型。
以秦山二期壓水堆為參攷堆型，對壓水堆環形燃料結構進行熱工水力分析方法研究。應用SAAF程序分析瞭從11×11到15×15等5種不同排列方式中不同呎吋的環形燃料棒的熱工水力性能，綜閤最小偏離泡覈沸騰比、壓降和燃料芯塊溫度等參數確定瞭環形燃料組件最佳排列方式為13×13。本文研究結果為相關專業分析提供瞭初始計算模型。
이진산이기압수퇴위삼고퇴형，대압수퇴배형연료결구진행열공수력분석방법연구。응용SAAF정서분석료종11×11도15×15등5충불동배렬방식중불동척촌적배형연료봉적열공수력성능，종합최소편리포핵비등비、압강화연료심괴온도등삼수학정료배형연료조건최가배렬방식위13×13。본문연구결과위상관전업분석제공료초시계산모형。
A typical Qinshan Phase‐Ⅱ PWR plant was selected as the base case for methodology study of thermal‐hydraulic analysis for the best array of annular fuel assembly applied in the PWR core .A range of arrays from 11 × 11 to 15 × 15 for differ‐ent sizes was investigated by using a sub‐channel analyzer named SAAF .On the consid‐eration of minimum departure from nucleate boiling ratios , pressure drops and fuel temperatures ,the most promising option was found to be the 13 × 13 array of annular fuel assembly .The calculation results in this paper provide initial calculation model for correlative analysis .
