杨百翰大学熔盐微堆的中子分析

Collin Bradford, Edward Mercado, Braden Clayton, LaGrande Gunnell, Andrew Larsen, Matthew Memmott
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摘要

背景:随着对可靠和清洁能源的需求不断增长,杨百翰大学的研究人员创造了一种熔盐微反应堆(MSMR)概念,以帮助满足世界日益增长的能源需求。MSMR的额定功率为45兆瓦,并且能够仅通过传导被动地消散所有衰变热。方法:本文采用蒙特卡罗中子电子学代码OpenMC和ENDF/B-VII模拟了MSMR的中子行为。1 .稳态条件下的截面库。本工作讨论的具体特性有:keff、功率分布、轴向和径向峰值功率因数、反应性多普勒系数和慢化剂温度反馈系数。结果:在稳态运行条件下,keff计算值为1.07091±0.00087,表明该配置可以达到临界状态。轴向峰值功率因数为1.003,径向峰值功率因数为1.45。分别通过补偿燃料和慢化剂的温度来计算反馈。反应性的多普勒系数为-12.585 pcm/K,慢化剂温度系数为-0.34332 pcm/K。结论:值得注意的是,负反应性的最大贡献者来自燃料盐,而不是慢化剂,进一步证明了反应堆的安全性。未来的工作将包括对堆芯进行全面的中子优化、燃料燃烧分析和探索合适的可燃中子毒药。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Neutronic analysis of the BYU molten salt micro reactor
Background: With the rising need for reliable and clean energy, researchers at Brigham Young University created a molten salt microreactor (MSMR) concept to help meet the world’s growing energy demands. The MSMR is rated at 45 MWth and is uniquely capable of passively dissipating all decay heat using conduction only. Methods: This work presents the results of the simulated neutronic behavior of the MSMR using the Monte Carlo neutronics code OpenMC with the ENDF/B-VII.1 cross-section library at steady state conditions. The specific characteristics discussed in this work are: keff, power profile, axial and radial peak power factors, Doppler coefficient of reactivity, and the moderator temperature feedback coefficient. Results: At steady state operating conditions, keff was calculated to be 1.07091 ± 0.00087 indicating that this configuration can achieve criticality. The axial peaking power factor was found to be 1.003 and the radial peaking power factor was found to be 1.45. Feedbacks were calculated by offsetting the temperature of the fuel and the moderator respectively. Doppler coefficient of reactivity to be -12.585 pcm/K and the moderator temperature coefficient of reactivity to be -0.34332 pcm/K. Conclusions: It is worth noting that the largest contributor of the negative reactivity comes from the fuel salt and not the moderator, further demonstrating the safety of the reactor. Future work will include a full neutronic optimization of the core, fuel burn up analysis, and exploration of a suitable burnable neutron poison.
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