首页> 外文会议>14th International Conference on Nuclear Engineering 2006(ICONE14) vol.3 >REACTOR CONTROLLABILITY OF 3-REGION-CORE MOLTEN SALT REACTOR SYSTEM — A STUDY ON LOAD FOLLOWING CAPABILITY
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REACTOR CONTROLLABILITY OF 3-REGION-CORE MOLTEN SALT REACTOR SYSTEM — A STUDY ON LOAD FOLLOWING CAPABILITY

机译:三区核熔盐反应器系统的反应堆可控性—负荷跟踪能力研究

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This paper reports the result of a unsteady analysis under the case of heat removal change and discusses the load following capability of the 3-region-core MSR system by using a numerical model developed by the authors. In the analysis, the "reactor- slaved-to-turbine" control technique which is recently utilized in the PWRs is applied to the 3-region-core MSR control. The following results were obtained in this study. 1. In the range of heat removal change (Q_c/P_0) 50 to 150%, the reactor can follow the steam turbine load autonomously. Furthermore, the stabilization times of all of the reactor parameters such as temperature, neutron ux es, delayed neutron precursors and reactor power are within 1000s approximately. 2. Fuel salt inlet temperature in the all of the cases of heat removal change uctuates immediately after the heat removal change; subsequently, it converge to the initial inlet temperature, 833K. 3. In the case of heat removal change Q_c/P_0=150%, fuel salt inlet temperature is below the solidi cation point of the fuel salt. Thus, in this case, we have to raise the inlet temperature by using other reactor control techniques like control rod manipulation and fuel salt o w control. 4. At the case of heat removal change Q_c/P_0=50%, temperatures, neutron ux es and delayed neutron precursor densities are decreased caused by the heat removal change. However their local elevations and drops are not occurred. From these results mentioned here, the 3-region-core MSR system has high nuclear and thermal safeties and good load following capability. Furthermore, the "reactor-slaved-to-turbine" control technique which is utilized in the PWRs is effective reactor control technique for the 3-region-core MSR system.
机译:本文报告了在换热情况下的非稳态分析结果,并通过使用作者开发的数值模型讨论了三区核MSR系统的负荷跟随能力。在分析中,最近在PWR中使用的“反应器从汽轮机”控制技术应用于3区域核MSR控制。在这项研究中获得了以下结果。 1.在除热量变化(Q_c / P_0)为50%到150%的范围内,反应堆可以自动跟随汽轮机负荷。此外,所有反应堆参数(例如温度,中子通量,延迟的中子前体和反应堆功率)的稳定时间大约在1000 s之内。 2.在所有排热变化情况下,燃油盐入口温度在排热变化后立即开始变化;随后,它收敛到初始入口温度833K。 3.在排热变化Q_c / P_0 = 150%的情况下,燃油盐入口温度低于燃油盐的凝固点。因此,在这种情况下,我们必须通过使用其他反应堆控制技术(例如控制棒操纵和燃料盐流量控制)来提高进口温度。 4.在除热变化Q_c / P_0 = 50%的情况下,由于除热变化导致温度,中子通量和延迟的中子前体密度降低。但是,它们不会发生局部升高和下降。从这里提到的这些结果来看,三区核MSR系统具有很高的核安全和热安全性以及良好的负荷跟随能力。此外,在压水堆中使用的“反应器从汽轮机”控制技术是用于三区核MSR系统的有效反应堆控制技术。

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