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Simulation of Safety and Transient Analysis of a Pressurized Water Reactor using the Personal Computer Transient Analyzer

机译:用计算机瞬态分析仪模拟压水堆的安全和瞬态分析

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Safety and transient analyses of a pressurised water reactor (PWR) using the Personal Computer Transient Analyzer (PCTRAN) simulator was carried out. The analyses presented a synergistic integration of a numerical model; a full scope high fidelity simulation system which adopted point reactor neutron kinetics model and movable boundary two phase fluid models to simplify the calculation of the program, so it could achieve real-time simulation on a personal computer. Various scenarios of transients and accidents likely to occur at any nuclear power plant were simulated. The simulations investigated the change of signals and parameters vis a vis loss of coolant accident, scram, turbine trip, inadvertent control rod insertion and withdrawal, containment failure, fuel handling accident in auxiliary building and containment, moderator dilution as well as a combination of these parameters. Furthermore, statistical analyses of the PCTRAN results were carried out. PCTRAN results for the loss of coolant accident (LOCA) caused a rapid drop in coolant pressure at the rate of 21.8KN/m2/sec triggering a shutdown of the reactor protection system (RPS), while the turbine trip accident showed a rapid drop in total plant power at the rate of 14.3 MWe/sec causing a downtime in the plant. Fuel handling accidents mimic results showed release of radioactive materials in unacceptable doses. This work shows the potential classes of nuclear accidents likely to occur during operation in proposed reactor sites. The simulations are very appropriate in the light of Nigeria’s plan to generate nuclear energy in the region of 1000 MWe from reactors by 2017.
机译:使用个人计算机瞬态分析仪(PCTRAN)模拟器对压水堆(PWR)进行了安全和瞬态分析。分析显示了数值模型的协同整合。一种全范围高保真仿真系统,采用点反应堆中子动力学模型和可移动边界两相流体模型简化了程序的计算,因此可以在个人计算机上实现实时仿真。模拟了任何核电厂可能发生的各种瞬态和事故情景。仿真研究了信号和参数的变化,以了解冷却剂损失事故,急停,涡轮跳闸,无意中控制杆插入和撤出,安全壳故障,辅助建筑物和安全壳中的燃料处理事故,减速剂稀释以及这些因素的组合参数。此外,对PCTRAN结果进行了统计分析。 PCTRAN的冷却液损失事故(LOCA)结果导致冷却液压力以21.8KN / m 2 / sec的速度快速下降,触发了反应堆保护系统(RPS)的关闭,涡轮机跳闸事故显示出工厂总功率以14.3 MWe / sec的速度迅速下降,导致工厂停机。模拟燃料处理事故的结果表明,放射性物质以不可接受的剂量释放。这项工作表明拟议的反应堆场址在运行期间可能发生的核事故的潜在类别。根据尼日利亚计划在2017年前从反应堆中产生1000 MWe核能的计划,这种模拟非常合适。

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