Neutron-Physical Model Impact on the Calculation of a Serious Accident with Sodium Boiling in a Fast Reactor


如何引用文章

全文:

开放存取 开放存取
受限制的访问 ##reader.subscriptionAccessGranted##
受限制的访问 订阅存取

详细

A comparative analysis is made of calculations of a loss-of-coolant accident in a 1500 MW(t) fast reactor. The COREMELT code with different neutron-physical modules RADAR3D and RAKAR2D and the same thermohydraulic module COREMELT are used. The computational results are used as a basis for comparing the self-protection of a reactor with a sodium cavity at the top of the core for the case of a serious accident with coolant boiling. The effect of the diffusion and transport modules of the spatial neutron-physics models on the calculation is analyzed.

作者简介

Yu. Ashurko

State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Obninsk

A. Volkov

State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Obninsk

K. Raskach

State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Obninsk

N. Solomonova

State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Obninsk

补充文件

附件文件
动作
1. JATS XML

版权所有 © Springer Science+Business Media, LLC, 2017