Conversion of high enriched uranium in thorium-232-based oxide fuel for light and heavy water reactors: MOX-T fuel

被引:12
|
作者
Vapirev, EI
Dimitrov, VI
Jordanov, TJ
Christoskov, ID
机构
[1] Faculty of Physics, Sofia University
关键词
D O I
10.1016/S0029-5493(96)01285-X
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
This paper discusses the possibility of using military high enriched uranium and plutonium in thorium oxide fuel for light and heavy water reactors (LWRs and HWRs). It is shown that such a fuel has several important advantages: (i) Pu-239 and other long-living actinides are generated in quantities which are at least 100 times less than in conventional fuel; (ii) neutron emission is lower by a factor of more than 100; (iii) U-233 is generated and burnt (the conversion factor for LWRs is 0.64-0.68 and for HWRs about 0.88); (iv) thorium is utilized and the total available amount of nuclear fuel is increased. The problem of non-proliferation of fissile material is also discussed and it is shown that the supervision of such fuel does not differ essentially from the supervision of low enriched uranium fuel with plutonium generation
引用
收藏
页码:105 / 112
页数:8
相关论文
共 24 条
  • [21] Sensitivity Studies to Assess the Impact of Geometry and Operating/Boundary Condition Perturbations on Thermal-Hydraulic Behavior of Advanced Fuel Channels in Pressure Tube Heavy Water Reactors with Uranium and Thorium-Based Fuels
    Bromley, B. P.
    Cheng, Z.
    Nava Dominguez, A.
    Colton, A. V.
    NUCLEAR TECHNOLOGY, 2021, 207 (10) : 1511 - 1537
  • [22] Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods
    Wojtaszek, Daniel T.
    Bromley, Blair P.
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2024, 10 (03):
  • [23] Transient System Thermal-Hydraulic Assessment of Advanced Uranium- and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors-II: Full-Core Analyses
    Wang, S.
    Beuthe, T.
    Huang, X.
    Dominguez, A. Nava
    Bromley, B. P.
    Colton, A., V
    NUCLEAR TECHNOLOGY, 2021, 207 (04) : 494 - 520
  • [24] Transient System Thermal-Hydraulic Assessment of Advanced Uranium- and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors-I: Two-Channel Analyses
    Wang, S.
    Beuthe, T.
    Huang, X.
    Dominguez, A. Nava
    Colton, A., V
    Bromley, B. P.
    NUCLEAR TECHNOLOGY, 2021, 207 (04) : 469 - 493