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作 者:彭敏俊
机构地区:[1]哈尔滨工程大学动力与核能工程学院,黑龙江哈尔滨150001
出 处:《哈尔滨工程大学学报》2005年第6期717-721,831,共6页Journal of Harbin Engineering University
摘 要:船用压水堆核动力装置采用双恒定运行方案,在稳态功率变化时必须保持冷却剂平均温度和蒸汽压力都恒定,因而控制策略较为复杂.文章以假想船用核动力装置为例,探讨了双恒定运行方案的基本控制策略,并采用RE-TRAN-02程序分别对主机快速升负荷、主机甩负荷和主机全速正倒车等工况下核蒸汽供应系统的热工水力瞬态过程进行分析.计算结果表明,装置负荷在20%~100%额定满功率范围内变化时,控制策略能够维持冷却剂平均温度和蒸汽压力的恒定,并满足反应堆热工安全性的要求.The control strategy challenge of a marine pressurized water reactor (PWR) nuclear power plant (NPP) under ideal steady-state programming is that both coolant average temperature and fresh steam pressure should remain constant as the plant load varies. Here, the basis control strategy for a marine PWR NPP under ideal steady-state programming was discussed. The dynamic performances of a nuclear steam supply system under varying conditions including rapid main turbine load-rise, turbine trip, and full speed reverse, were evaluated by means of RETRAN-02 code. Results show that the control strategy can maintain both coolant average temperature and fresh steam constant with the plant load ranging between 20 to 100 percent full power, while the core thermal safety limits satisfy the requirements of reactor safety.
分 类 号:TL36[核科学技术—核技术及应用]
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