Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

被引:16
|
作者
Sun, Kaichao [1 ]
Hu, Lin-Wen [1 ]
Forsberg, Charles [1 ]
机构
[1] MIT, 77 Massachusetts Ave, Cambridge, MA 02139 USA
关键词
D O I
10.1115/1.4032873
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The fluoride-salt-cooled high-temperature reactor (FHR) is a new reactor concept, which combines low-pressure liquid salt coolant and high-temperature tristructural isotropic (TRISO) particle fuel. The refractory TRISO particle coating system and the dispersion in graphite matrix enhance safeguards (nuclear proliferation resistance) and security. Compared to the conventional high-temperature reactor (HTR) cooled by helium gas, the liquid salt system features significantly lower pressure, larger volumetric heat capacity, and higher thermal conductivity. The salt coolant enables coupling to a nuclear air-Brayton combined cycle (NACC) that provides base-load and peak-power capabilities. Added peak power is produced using jet fuel or locally produced hydrogen. The FHR is, therefore, considered as an ideal candidate for the transportable reactor concept to provide power to remote sites. In this context, a 20-MW (thermal power) compact core aiming at an 18-month once-through fuel cycle is currently under design at Massachusetts Institute of Technology (MIT). One of the key challenges of the core design is to minimize the reactivity swing induced by fuel depletionl, since excessive reactivity will increase the complexity in control rod design and also result in criticaity risk during the transportation process. In this study, burnable poison particles (BPPs) made of B4C with natural boron (i.e., 20% 10B content) are adopted as the key measure for fuel cycle optimization. It was found that the overall inventory and the individual size of BPPs are the two most important parameters that determine the evolution path of the multiplication factor over time. The packing fraction (PF) in the fuel compact and the height of active zone are of secondary importance. The neutronic effect of Li-6 depletion was also quantified. The 18-month once-through fuel cycle is optimized, and the depletion reactivity swing is reduced to 1 beta. The reactivity control system, which consists of six control rods and 12 safety rods, has been implemented in the proposed FHR core configuration. It fully satisfies the design goal of limiting the maximum reactivity worth for single control rod ejection within 0.8 beta and ensuring shutdown margin with the most valuable safety rod fully withdrawn. The core power distribution including the control rod's effect is also demonstrated in this paper.
引用
收藏
页数:10
相关论文
共 50 条
  • [1] Study of tritium transport characteristics in a transportable fluoride-salt-cooled high-temperature reactor
    Qin, Hao
    Wang, Chenglong
    Qiu, Suizheng
    Zhang, Dalin
    Tian, Wenxi
    Su, G. H.
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2018, 42 (04) : 1536 - 1550
  • [2] Uncertainty Analysis of Transportable Fluoride-Salt-Cooled High Temperature Reactor (TFHR)
    Wang C.
    Hu L.
    Qiu S.
    Su G.
    Tian W.
    Hedongli Gongcheng/Nuclear Power Engineering, 2017, 38 (03): : 168 - 171
  • [3] Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor
    Wang, Chenglong
    Liu, Limin
    Liu, Minghao
    Zhang, Dalin
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    ANNALS OF NUCLEAR ENERGY, 2017, 109 : 458 - 468
  • [4] Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology
    Scarlat, Raluca O.
    Laufer, Michael R.
    Blandford, Edward D.
    Zweibaum, Nicolas
    Krumwiede, David L.
    Cisneros, Anselmo T.
    Andreades, Charalampos
    Forsberg, Charles W.
    Greenspan, Ehud
    Hu, Lin-Wen
    Peterson, Per F.
    PROGRESS IN NUCLEAR ENERGY, 2014, 77 : 406 - 420
  • [5] Study on the safety characteristics of fluoride-salt-cooled high-temperature advanced reactor
    Lv, Xindi
    Zhang, Dalin
    Li, Xinyu
    Zhou, Xingguang
    Jiang, Dianqiang
    Su, Guanghui
    Tian, Wenxi
    Qiu, Suizheng
    ANNALS OF NUCLEAR ENERGY, 2024, 200
  • [6] Transient Safety Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor Using RELAP5-3D
    Wang, Chenglong
    Sun, Kaichao
    Hu, Lin-wen
    Zhang, Dalin
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    NUCLEAR TECHNOLOGY, 2017, 198 (01) : 1 - 16
  • [7] Study on tritium transport characteristics in fluoride-salt-cooled high-temperature advanced reactor
    Li, Haoyang
    Zhang, Dalin
    Qin, Hao
    Li, Xinyu
    Deng, Jian
    Tian, Wenxi
    Su, Guanghui
    Qiu, Suizheng
    INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2024, 56 : 1101 - 1110
  • [8] Transient analysis of tritium transport characteristics in fluoride-salt-cooled high-temperature reactor
    Qin, Hao
    Wang, Chenglong
    Zhang, Dalin
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    PROGRESS IN NUCLEAR ENERGY, 2019, 117
  • [9] Tritium Management and Control Using Carbon in a Fluoride-Salt-Cooled High-Temperature Reactor
    Lam, Stephen T.
    Stempien, John
    Ballinger, Ronald
    Forsberg, Charles
    FUSION SCIENCE AND TECHNOLOGY, 2017, 71 (04) : 644 - 648
  • [10] Analysis of different nuclear data libraries on the Fluoride-salt-cooled high-temperature reactor
    Maul, Lance
    NUCLEAR ENGINEERING AND DESIGN, 2018, 335 : 314 - 325