Computational Aspects of Core Neutronics Calculation of Sodium-Cooled Fast Reactor at the Core Destruction Stage

被引：0

作者：

Koltashev, D. A. ^{[1
]}

Mosunova, N. A. ^{[1
]}

Strizhov, V. F. ^{[1
]}

Butov, A. A. ^{[2
]}

Klimonov, I. A. ^{[2
]}

Chukhno, V. I. ^{[2
]}

Usov, E. V. ^{[2
]}

机构：

[1] Russian Acad Sci RAS, Nucl Safety Inst, IBRAE, Moscow, Russia

[2] Russian Acad Sci RAS, Nucl Safety Inst, IBRAE, Novosibirsk Branch, Novosibirsk, Russia

来源：

ATOMIC ENERGY | 2022年 / 132卷 / 04期

关键词：

Computational aspects - Core neutronics - Integrated codes - Neutronic calculations - Neutronics - Operational algorithms - Severe accident;

D O I：

10.1007/s10512-023-00930-7

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 approaches used in the EUCLID/V2 integrated code to calculate the core neutronics of a sodium-cooled fast reactor at the core destruction stage are described. Information is offered about the features of the operational algorithms of the SAFR severe accident module and the DN3D neutronics module. The ability of the integrated code to correctly calculate the processes involving core destruction is shown for an LOC accident.

引用

页码：212 / 218

页数：7

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