Study of the Self-Controllability for the Fast Reactor Core with High-Thermal-Conductivity Fuel

被引:3
作者
Ishizu, Tomoko [1 ,2 ]
Yokoyama, Tsugio [2 ]
Endo, Hiroshi [1 ]
Tokiwai, Moriyasu [3 ]
Ninokata, Hisashi [2 ]
机构
[1] Japan Nucl Energy Safety Org JNES, Nucl Energy Syst Safety Div, Minato Ku, Tokyo 1050001, Japan
[2] Tokyo Inst Technol, Nucl Reactors Res Lab, Meguro Ku, Tokyo 1528550, Japan
[3] CRIEPI, Komae Lab, Komae, Tokyo 2018511, Japan
关键词
aluminum alloy fuel; high thermal conductivity; self-controllability; ULOF limit line; UTOP limit line; safety map; CDA;
D O I
10.3327/jnst.47.684
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 tolerance capability against ATWS for the FBR core with metallic fuel can be improved by employing a fuel with high thermal conductivity (HTC fuel) instead of the conventional metallic fuel, U-Pu-Zr. To investigate the self-controllability for the HTC-fueled core with U-Pu-Al alloy fuel, having one order of magnitude higher thermal conductivity than that of the U-Pu-Zr, the core employing the U-Pu-Al fuel was evaluated against ULOF and UTOP. Based on the systematic calculation, it was found that the larger temperature margin between the steady state and ULOF/UTOP conditions caused the excellent tolerance capability against ULOF and UTOP for the HTC-fueled core compared with that for the Zr-alloy-fueled core. Also, the conditions of the core reactivity coefficients required for neither fuel melting nor coolant boiling were investigated by using a "self-controllability map" consisting of effective fuel and coolant reactivities. As a result, the self-controllable region was found to be expanded especially for UTOP in the case of the HTC-fueled core.
引用
收藏
页码:684 / 697
页数:14
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