Behavior of VVER fuel rods tested under severe accident conditions in the CODEX facility

被引：14
|
作者：
Hózer, Z
Maróti, L
Windberg, P
Matus, L
Nagy, I
Gyenes, G
Horváth, M
Pintér, A
Balaskó, M
Czitrovszky, A
Jani, P
Nagy, A
Prokopiev, O
Tóth, B
机构：
[1] KFKI Atom Energy Res Inst, H-1525 Budapest, Hungary
[2] Res Inst Solid State Phys & Opt, H-1525 Budapest, Hungary
[3] New Mexico State Univ, Las Cruces, NM 88001 USA
[4] Joint Res Ctr, Inst Energy, NL-1755 ZG Petten, Netherlands
来源：
NUCLEAR TECHNOLOGY | 2006年 / 154卷 / 03期
关键词：
severe accident; VVER reactor; core degradation;
D O I：
10.13182/NT06-A3735
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 early phase of severe accidents in VVER reactors was simulated in the CODEX (COre Degradation EXperiment)facility with electrically heated fuel rod bundles. The selected test conditions and applied measurement techniques made possible the observation of some specific phenomena, such as the protective role of oxide scale during quenching of high-temperature bundles, the composition of gases produced during the oxidation of boron-carbide control rods, and the interlink between the aerosol release and the oxidation process. The general behavior of the VVER bundles did not differ significantly from that of the Western-design light water reactor bundles tested under similar high-temperature conditions, but the experiments emphasized that the application of VVER-specific material properties and models is essential for comprehensive numerical simulations.
引用
收藏
页码：302 / 317
页数：16
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