百万千瓦级钠冷快堆热工参数研究分析  

Research and Analysis of Thermal Parameter of Million-kilowatt Sodium-cooled Fast Reactor

作　　者：丁铜伟[1] 陈薇 王文杰 DING Tongwei;CHEN Wei;WANG Wenjie(Nuclear Technology Support Center,National Defense Technology Industry Ministry,Beijing 100070,China;China Nuclear Power Development Center,National Energy Administration,Beijing 100045,China;China Productivity Center for Machinery Co.,Ltd.,Beijing 100044,China)

机构地区：[1]国家国防科技工业局核技术支持中心,北京100070 [2]国家能源局中国核电发展中心,北京100045 [3]中机生产力促进中心有限公司,北京100044

出　　处：《原子能科学技术》2025年第S1期89-95,共7页Atomic Energy Science and Technology

摘　　要：百万千瓦级钠冷快堆是一体化闭式循环钠冷快堆核能系统(一体化快堆)必须突破的关键一环,但是由于某些方面的原因,国内至今还没有百万千瓦级钠冷快堆机组。中国实验快堆奠定了我国钠冷快堆的基础和范畴,百万千瓦级钠冷快堆是中国实验快堆的优化和改进,二者的热传输机理一致,因此本文借鉴经中国实验快堆验证过的传热模型,建立百万千瓦级钠冷快堆的传热模型,并通过中国实验快堆及法国钠冷快堆的运行数据对其准确性进行了验证。同时,本文参考了国际上钠冷快堆的工艺系统参数,结合已有的相关研究结果,在确保反应堆安全的前提下,着重考虑了系统的可行性、设备制造成本及可靠性,研究分析了百万千瓦级钠冷快堆的热工参数。确定的热工参数综合考虑了经济性、有效性、安全性和可实现性,可为我国发展百万千瓦级钠冷快堆提供参考。The million-kilowatt sodium-cooled fast reactor is a mature and commercially promising reactor type,playing a key role in the integrated closed sodium-cooled fast reactor nuclear energy system(integrated fast reactor).Currently,in China,there is no such million-kilowatt sodium-cooled fast reactor unit because of some special factors.The China Experimental Fast Reactor(CEFR)has formed the basis for sodium-cooled fast reactors in China.The million-kilowatt sodium-cooled fast reactor represents an optimization and improvement of the CEFR,sharing the same heat-transfer mechanism.This study used the heat-transfer model validated by CEFR,and set up the reactor core heat transfer model,heat exchange equipment heat transfer model,thermoelectric conversion model,and ultimate heat sink model for the million-kilowatt sodium-cooled fast.The model was validated using two sets of actual operational data from the CEFR at 40%rated power and 100%rated power,and the relative error of electric power was found to be less than 1.3%.The reactor core heat transfer model was validated by substituting the core data from the French million-kilowatt sodium-cooled fast reactor(Super Phenix)into the model and comparing the results with the calculated values.The discrepancy between the reactor core flow rate and the actual flow rate is found to be within 2%.These data all confirm the correctness of the model.This paper conducted a thermal parameter research analysis on the million-kilowatt sodium-cooled fast reactor by referencing the process system parameters of overseas large-scale sodium-cooled fast reactors,such as Russian BN-600 and BN-800,and France Phenix and Super Phenix.By integrating relevant international research findings,the study aims to explore and analyze the thermal-hydraulic characteristics of the sodium-cooled fast reactor at the megawatt level,thereby providing theoretical support and practical guidance for the development of sodium-cooled fast reactor technology in China.Under the premise of ensuring reactor safety,with a

关 键 词：百万千瓦级钠冷快堆 热工参数 一体化快堆 

分 类 号：TL334[核科学技术—核技术及应用]