RTDP方法在大型先进压水堆热工设计中的应用初步研究  

Preliminary Research on RTDP Methodology for Advanced LPP Thermal-hydraulic Design

作　　者：杨萍[1] 贾红轶[1] 王喆[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《原子能科学技术》2013年第7期1182-1186,共5页Atomic Energy Science and Technology

摘　　要：偏离泡核沸腾(DNB)设计基准是反应堆热工水力设计中的重要基准之一,为评价该设计基准是否满足热工水力设计要求,首先需确定堆芯偏离泡核沸腾比(DNBR)设计限值。本工作详细论述了使用统计学方法确定运行参数及核设计参数等不确定性的RTDP原理,并应用该方法和堆芯子通道分析程序对大型先进压水堆DNBR设计限值及含汽率限值进行计算并给出结论,为DNBR设计基准的验证提供了关键判据。Departure from nucleate boiling（DNB） design basis is one of the most important basis for reactor core thermal-hydraulic design.In order to evaluate whether the DNB design basis meets the demand of thermal-hydraulic design,the departure from nucleate boiling ratio（DNBR） design limit should be determined first.The RTDP methodology was described detailedly,in which the uncertainties of operating parameters and nuclear design parameters were statistically combined.Then the RTDP methodology and a reactor subchannel code were applied to calculate the DNBR design limit and quality limit for LPP.The conclusions were presented to provide the key acceptable criterion for DNBR design basis.

关 键 词：RTDP DNBR 设计限值 热工水力设计 

分 类 号：TL333[核科学技术—核技术及应用]