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液态熔盐堆运行安全特性初步研究
引用本文:魏泉,梅龙伟,战志超,郭威,陈金根,蔡翔舟.液态熔盐堆运行安全特性初步研究[J].原子能科学技术,2014,48(12):2280-2286.
作者姓名:魏泉  梅龙伟  战志超  郭威  陈金根  蔡翔舟
作者单位:1.中国科学院大学,北京100049;2.中国科学院 上海应用物理研究所,上海201800;3.中国科学院 钍基熔盐堆核能系统卓越创新中心,上海201800;4.中国科学院 核辐射与核能技术重点实验室,上海201800
基金项目:中国科学院TMSR战略先导科技专项资助(XDA02010100);国家自然科学基金重点项目资助(91326201)
摘    要:液态燃料反应堆与固态燃料反应堆相比,原理上有较大不同。液态熔盐堆中由于燃料流动带走缓发中子先驱核在堆外衰变导致堆芯反应性降低,且裂变产物在堆外回路中衰变也会引起一回路发热。本文使用熔盐堆中子动力学程序Cinsf1D探讨2 MW熔盐堆的临界动力学特性和安全特性,研究零功率临界下不同熔盐流速启泵和停泵导致的缓发中子先驱核流失所需改变的控制棒棒位。同时还计算了2 MW恒定功率情况下稳态运行及降低流速时一回路温度分布,并模拟了2 MW额定功率下停泵事件。停泵后由于缓发中子损失减少反应堆功率先缓慢增加,然后迅速降低到接近余热水平。停泵后堆芯温度缓慢增加后稳定在安全值以内,说明熔盐堆具有本征安全性。

关 键 词:熔盐堆    中子动力学    反应性    本征安全    功率

Preliminary Study on Safety Characteristics of Molten Salt Reactor
WEI Quan,MEI Long-wei,ZHAN Zhi-chao,GUO Wei,CHEN Jin-gen,CAI Xiang-zhou.Preliminary Study on Safety Characteristics of Molten Salt Reactor[J].Atomic Energy Science and Technology,2014,48(12):2280-2286.
Authors:WEI Quan  MEI Long-wei  ZHAN Zhi-chao  GUO Wei  CHEN Jin-gen  CAI Xiang-zhou
Affiliation:1.University of Chinese Academy of Sciences, Beijing 100049, China;2.Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China;3.Center for Excellence in TMSR Energy System, Chinese Academy of Sciences, Shanghai 201800, China;4.Key Laboratory of Nuclear Radiation and Nuclear Energy Technology,Chinese Academy of Sciences, Shanghai 201800, China
Abstract:Compared with solid fuel reactors, there are differences in physics for liquid fuel reactor. As for molten salt reactor (MSR), due to fuel flow in primary loop, the delayed neutron precursors and fission product partly decay out of core, resulting in reactivity loss as well as heat generation in the primary loop. In this paper, the critical dynamics and safety characteristics of MSR were investigated using Cinsf1D code. Considering the loss of delayed neutrons under different fuel flow speeds at zero-power, the corresponding control rod positions were calculated under pump start and stop conditions. Keeping reactor power at 2 MW, the temperature and power were computed for the primary loop system. Finally, the pump stop accident was simulated from rated power 2 MW. After pump stop, the reactor power increases slightly due to the reduction of delayed neutron loss at initial time and then it decreases to approach the decay heat power level quickly. The temperature in core increases slowly and reaches to a balance within safety range. It can be concluded that MSR has intrinsic safety.
Keywords:molten salt reactor  neutron dynamics  reactivity  intrinsic safety  power
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