首页|期刊导航|四川大学学报(自然科学版)|球床模块式高温气冷堆稳态与瞬态热工水力分析

球床模块式高温气冷堆稳态与瞬态热工水力分析OA

Steady-state and transient thermal-hydraulic analysis for pebble-bed modular high temperature gas cooled reactor

中文摘要英文摘要

本文探究了一种基于RELAP5程序的球床模块式高温气冷堆模拟分析方法.以山东石岛湾高温气冷堆核电站示范工程(High Temperature Reactor-Pebble bed Module,HTR-PM)为研究对象,依据其系统特性进行模型简化与模块划分,建立了包括反应堆堆芯流道、燃料热构件、横向导热构件及蒸汽发生器的全回路系统模型.基于所建HTR-PM模型,开展100%额定功率和50%额定功率下的平衡堆芯热工水力分析,同时研究了旁流份额对堆芯热效应的影响;在此基础上,选择保守旁流份额开展全厂断电叠加未能停堆(Anticipated Transient with-out Scram,ATWS)事故的模拟.结果表明:针对稳态平衡堆芯计算得到的回路主参数及堆芯燃料、冷却剂的温度分布与参考软件THERMIX的计算结果吻合良好;反应堆结构设计中,过高的旁流份额会导致堆芯局部燃料及冷却剂温度过高,通过优化堆芯结构降低旁流份额对保障堆芯热工安全具有重要意义;全厂断电ATWS事故中,燃料最高温度低于设计限值,再次验证球床模块式高温气冷堆的固有安全性.本研究基于独立的系统分析程序,实现对现有球床模块式高温气冷堆分析工具的补充和扩展;提供的详细的建模分析方法与丰富的数据,可为RELAP5程序在球床模块式高温气冷堆的复杂热工水力与事故分析的全面应用提供参考.

The pebble-bed modular high-temperature gas-cooled reactor(HTGR)is one of the most promis-ing technologies for meeting the requirements of fourth-generation nuclear energy systems.The high tempera-ture reactor-pebble bed module(HTR-PM)demonstration plant,located in Shidao Bay,Shandong Prov-ince,is the world's first modular high-temperature gas-cooled reactor nuclear power plant.In this paper,a RELAP5-based simulation and analysis method for pebble-bed HTGRs is investigated.A plant-level system model based on the system characteristics of HTR-PM is established,which includes the reactor core flow paths,the fuel thermal components,the transverse heat-conducting components and the steam generator.Us-ing this model,steady-state thermal-hydraulic analysis was carried out,and the impact of bypass flow frac-tions on core thermal performance was conducted.The steady-state thermal-hydraulic analyses of 100%full power(100%FP)and 50%full power(50%FP)conditions demonstrate strong agreement between RELAP5 and THERMIX.The impact of bypass flow fractions on the core thermal effect showed that a 10%increase in bypass flow fraction elevates the average core temperature by approximately 40~60℃,with local hot spot temperature rises above 90℃,indicating that the bypass fraction plays an important role in the core thermal effect.Optimizing structural design to reduce the bypass flow fraction is of great significance for core thermal-hydraulic safety.Based on the steady-state results,conservative assumptions were adopted to simu-late the plant outage Anticipated Transient without Scram(ATWS)accident under rated power equilibrium core conditions.The strong negative temperature feedback coefficient of the HTR-PM was validated,demon-strating that peak fuel temperatures remained below the design limit of 1620℃during ATWS scenarios,once again confirming the inherent safety of pebble-bed modular HTGR.This study is based on an independent sys-tematic analysis program,which is a supplement and extension of the existing analysis tools for pebble-bed modular HTGRs;the study provides detailed modelling and analysis methodology with rich data,which can be used as a reference for further and comprehensive application of RELAP5 to the complex thermal-hydraulic and accident analysis of pebble-bed modular HTGRs.

张枫;刘伟;王朗;李雪琳;勾成俊;葛莉

四川大学原子核科学技术研究所,成都 610064华能核能技术研究院,上海 200126华能核能技术研究院,上海 200126华能核能技术研究院,上海 200126华能核能技术研究院,上海 200126四川大学原子核科学技术研究所,成都 610064

能源科技

HTR-PMRELAP5热工水力分析全厂断电ATWS

HTR-PMRELAP5thermal-hydraulic analysisplant outage ATWS

《四川大学学报(自然科学版)》 2026 (1)

139-147,9

山东省重点研发计划(科技示范工程)项目(2022SFGC0501)

10.19907/j.0490-6756.250089

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