摘要
应急给水系统(EFS)作为核电站专设安全设施之一,用于在其他给水系统事故的工况下导出反应堆冷却剂系统堆芯余热。其假设事故下的流量试验是核电站装料许可的关键性必要试验。调试中发现,EFS流量偏大,不满足准则要求。针对该问题,本工作建立了EFS热工水力模型,并将数值模拟结果与试验数据进行校核,确定了模型的可靠性。通过数值分析,提出EFS流量超准则的解决方案。进一步试验结果表明,EFS破口流量显著降低,完全符合验收准则。
The emergency feedwater system（EFS） was served as one of the engineer safeguard system to remove the residual heat of the reactor coolant system.The flowrate test of postulated accident scenarios was the key role of the fuel loading licensing for the nuclear power plants.The system flowrates were found to be larger than the acceptance criteria in one certain plant during the system test.The criteria broken reasons were analytically investigated and the system retrofits were proposed by numerical simulation which was validated by the test data.The experimental data show that the system flowrates after system retrofits decrease and meet the requirement of the acceptance criteria.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2012年第B09期277-282,共6页
Atomic Energy Science and Technology
基金
国家重大专项资助项目(2011ZX06004004-001)
关键词
应急给水系统
堆芯余热
反应堆冷却剂系统
调试
数值模拟
emergency feedwater system
residual heat of reactor core
reactor coolant system
test
numerical simulation
