Fission product precipitates in irradiated uranium carbonitride fuel

被引：6
|
作者：
Kleykamp, H [1 ]
机构：
[1] Forschungszentrum Karlsruhe, Inst Mat Forsch 1, D-76021 Karlsruhe, Germany
来源：
JOURNAL OF NUCLEAR MATERIALS | 2002年 / 300卷 / 2-3期
关键词：
D O I：
10.1016/S0022-3115(01)00741-3
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Austenitic steel-cladded uranium carbonitride fuel pins were irradiated in the BR2 up to 6.4% burnup. A cross-section of the pin RV 24 with the fuel composition UC0.86N0.09O0.05 was prepared for X-ray microanalysis of the fission product precipitates. Rare-earth oxide and U(Mo,Tc)C-2 phases were observed in the whole fuel region, Bright phases present in annular rings of the outer fuel zone were identified as U-2(Tc, Ru, Rh)C-2. Alkaline-earth oxide and U-Pd-Ni phases were shown in the fuel-cladding gap. The rare-earth and alkaline-earth fission products extracted the oxygen from the fuel matrix which became nearly oxygen free. The formation of nitrides could not be detected. (C) 2002 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：273 / 276
页数：4
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