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利用FDS团队(Fission&Fusion Design Study)开发的中子学与热工水力学耦合安全分析软件,对一种加速器驱动铅铋自然循环次临界反应堆的束流中断及束流超功率事故进行了模拟分析。计算结果表明:加速器驱动次临界洁净核能系统(Accelerator Driven Sub-critical System,ADS)次临界堆的功率对束流瞬变的响应几乎是瞬时的;事故工况下,自然循环会根据堆芯功率自动调整至重新达到稳定;失束时间越长,材料温度降得越低,功率瞬间恢复值越低,束流恢复后,材料温度回升的速度越快;束流200%超功率事故发生后堆芯功率最终稳定在初始功率值的192.2%,燃料温度增幅最大,为286 K,燃料和包壳不会发生损坏和熔化,冷却剂不会发生沸腾。
Based on the neutron and thermal-hydraulics coupling safety analysis software developed by the FDS (Fission & Fusion Design Study), a kind of accelerator-driven PbBi natural circulation sub-critical reactor beam interruption and beam super-power accident were simulated and analyzed. The calculated results show that the response of accelerator driven subcritical stacks to beam transient is nearly instantaneous. In the accident conditions, the natural circulation will depend on the core power Automatically adjusted to re-stabilize; the longer the time of de-bundling, the lower the temperature of the material, the lower the instantaneous power recovery value, the faster the temperature of the material recovered after the recovery of the beam; The core power eventually stabilized at 192.2% of the initial power value, with the maximum increase in fuel temperature of 286 K, without damage and melting of fuel and cladding, and no boiling of coolant.