Feasibility Study of 1/3 Thorium-Plutonium Mixed Oxide Core

被引:7
|
作者
Lau, Cheuk Wah [1 ]
Nylen, Henrik [1 ,2 ]
Bjork, Klara Insulander [1 ,3 ]
Sandberg, Urban [2 ]
机构
[1] Chalmers Univ Technol, Dept Appl Phys, Div Nucl Engn, S-41296 Gothenburg, Sweden
[2] Ringhals AB, S-43285 Varobacka, Sweden
[3] Thor Energy AS, N-0255 Oslo, Norway
关键词
FUELS; MOX; PERFORMANCE; DESIGN;
D O I
10.1155/2014/709415
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
Thorium-plutonium mixed oxide (Th-MOX) fuel has become one of the most promising solutions to reduce a large and increasing plutonium stockpile. Compared with traditional uranium-plutonium mixed oxide (U-MOX) fuels, Th-MOX fuel has higher consumption rate of plutonium in LWRs. Besides, thorium based fuels have improved thermomechanical material properties compared with traditional U-MOX fuels. Previous studies on a full Th-MOX core have shown reduced efficiency in reactivity control mechanisms, stronger reactivity feedback, and a significantly lower fraction of delayed neutrons compared with a traditional uranium oxide (UOX) core. These problems complicate the implementation of a full Th-MOX core in a similar way as for a traditional U-MOX core. In order to reduce and avoid some of these issues, the introduction of a lower fraction of Th-MOX fuel in the core is proposed. In this study, one-third of the assemblies are Th-MOX fuel, and the rest are traditional UOX fuel. The feasibility study is based on the Swedish Ringhals-3 PWR. The results show that the core characteristics are more similar to a traditional UOX core, and the fraction of delayed neutrons is within acceptable limits. Moreover, the damping of axial xenon oscillations induced by control rod insertions is almost 5 times more effective for the 1/3 Th-MOX core compared with the standard core.
引用
收藏
页数:10
相关论文
共 50 条
  • [1] Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors
    Mustafa, S. S.
    Amin, E. A.
    [J]. SCIENTIFIC REPORTS, 2019, 9 (1)
  • [2] Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors
    S. S. Mustafa
    E. A. Amin
    [J]. Scientific Reports, 9
  • [3] Thermal diffusivity and conductivity of thorium-plutonium mixed oxides
    Cozzo, C.
    Staicu, D.
    Somers, J.
    Fernandez, A.
    Konings, R. J. M.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 416 (1-2) : 135 - 141
  • [4] Study of Thorium-Plutonium Fuel for Possible Operating Cycle Extension in PWRs
    Bjork, Klara Insulander
    Lau, Cheuk Wah
    Nylen, Henrik
    Sandberg, Urban
    [J]. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2013, 2013
  • [5] Physical Analysis of the Heat Pipe Cooled Micro Nuclear Reactor Based on Thorium-Plutonium Mixed Fuel
    Wang, Feng
    Sun, Yuannan
    Liu, Bin
    [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2024, 45 (06): : 9 - 14
  • [6] Thermal-mechanical performance modeling of thorium-plutonium oxide fuel and comparison with on-line irradiation data
    Bjork, Klara Insulander
    Kekkonen, Laura
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2015, 467 : 876 - 885
  • [7] Conceptual study of axial offset fluctuations upon stepwise power changes in a thorium-plutonium core to improve load-following conditions
    Lau, Cheuk Wah
    Dykin, Victor
    Nylen, Henrik
    Bjork, Klara Insulander
    Sandberg, Urban
    [J]. ANNALS OF NUCLEAR ENERGY, 2014, 72 : 84 - 89
  • [8] X-ray absorption in plutonium uranium mixed oxide fuel: Thorium characterization
    Cozzo, C.
    Orlov, A.
    Borca, C.
    Degueldre, C.
    [J]. PROGRESS IN NUCLEAR ENERGY, 2014, 72 : 91 - 95
  • [9] Performance of thorium-based mixed-oxide fuels for the consumption of plutonium in current and advanced reactors
    Weaver, KD
    Herring, JS
    [J]. NUCLEAR TECHNOLOGY, 2003, 143 (01) : 22 - 36
  • [10] Neutronic analysis of the PBMR-400 full core using thorium fuel mixed with plutonium or minor actinides
    Acir, Adem
    Coskun, Hasan
    [J]. ANNALS OF NUCLEAR ENERGY, 2012, 48 : 45 - 50