Deformation of Experimental Fuel Pins with Improved Zirconium-Alloy Cladding in Reactor Tests

被引：0
|
作者：
Burukin, A. V. [1 ]
Dolgov, A. I. [1 ]
Izhutov, A. L. [1 ]
Il'in, P. A. [1 ]
Kalygin, V. V. [1 ]
Mokeichev, M. A. [1 ]
Ugryumov, A. V. [2 ]
Dolgov, Yu. N. [2 ]
机构：
[1] Res Inst Atom Reactors SSC RIAR, State Sci Ctr Russian Federat, Dimitrovgrad, Russia
[2] TVEL, Moscow, Russia
来源：
ATOMIC ENERGY | 2020年 / 128卷 / 03期
关键词：
Fuels;
D O I：
10.1007/s10512-020-00674-8
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：
A stand for inspecting experimental fuel pins in the cooling pool of the MIR.M1 reactor and methodological approaches to measuring the height and diameter of experimental fuel pins are described. The basic characteristics of the equipment used for performing measurements are described. The structural features of an experimental FA (EFA) and the test parameters of experimental fuel pins in an assembly in one of the loop facilities of the MIR reactor are presented. The results of a series of measurements of the diameter and height of irradiated fuel pins with cladding made from different zirconium alloys with different average fuel burnup over the EFA are shown.
引用
收藏
页码：191 / 195
页数：5
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