EVALUATION OF SOKRAT CODE POSSIBILITY TO MODEL URANIUM-DIOXIDE FUEL DISSOLUTION BY MOLTEN ZIRCONIUM

被引：4
|
作者：
Dolganov, K. S. [1 ]
Kiselev, A. E. [1 ]
Ryzhov, N. I. [1 ]
Tomashchik, D. Yu. [1 ]
Filippov, M. F. [1 ]
Chalyi, R. V. [1 ]
Yudina, T. A. [1 ]
Shevchenko, S. A. [2 ]
Yashnikov, D. A. [2 ]
Kozlova, N. A. [2 ]
机构：
[1] Russian Acad Sci IBRAE RAN, Nucl Safety Inst, Moscow, Russia
[2] Sci & Engn Ctr Nucl & Radiat Safety NTTs YaRB, Moscow, Russia
来源：
ATOMIC ENERGY | 2018年 / 125卷 / 02期
关键词：
UO2; ZIRCALOY;
D O I：
10.1007/s10512-018-0446-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：
A quantitative assessment is made of the possibilities of the SOKRAT code to model the dissolution of uranium dioxide fuel by zirconium cladding melt at the initial stage of a serious accident at NPP with VVER. The methodological approach for the assessment is based on the ASME V&V 20 standard and includes an uncertainty analysis. The results of local high-temperature experiments studying the kinetics of the process are used as a technical base.
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收藏
页码：82 / 90
页数：9
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