Email this article Neutron-Physical Model Impact on the Calculation of a Serious Accident with Sodium Boiling in a Fast Reactor
- Authors: Ashurko Y.M.1, Volkov A.V.1, Raskach K.F.1, Solomonova N.V.1
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Affiliations:
- State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)
- Issue: Vol 122, No 4 (2017)
- Pages: 217-225
- Section: Articles
- URL: https://journal-vniispk.ru/1063-4258/article/view/248461
- DOI: https://doi.org/10.1007/s10512-017-0259-3
- ID: 248461
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Abstract
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.
About the authors
Yu. M. Ashurko
State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)
Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk
A. V. Volkov
State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)
Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk
K. F. Raskach
State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)
Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk
N. V. Solomonova
State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI)
Email: j-atomicenergy@yandex.ru
Russian Federation, Obninsk
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