Validation of the severe accident module of the EVKLID/V2 integral code on the base of experiments with fission products release and dissociation of nitride fuel-Reference-Cited by-同舟云学术

Validation of the severe accident module of the EVKLID/V2 integral code on the base of experiments with fission products release and dissociation of nitride fuel

Published:2024-08-21 Issue: Volume: Page:
ISSN:1063-4258
Container-title:Atomic Energy
language:en
Short-container-title:At Energy

Author:

Zhdanov V. S.,Klimonov I. A.,Kudashov I. G.,Mosunova N. A.,Strizhov V. F.,Sycheva T. V.,Usov E. V.,Chukhno V. I.,Kireev G. A.,Krivov M. P.,Skupov M. V.

Publisher

Springer Science and Business Media LLC

Link

https://link.springer.com/content/pdf/10.1007/s10512-024-01115-6.pdf

Reference17 articles.

1. Butov, A.A., Zhdanov, V.S., Klimonov, I.A.: The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor. Thermal Engineering 55(4), 302–308 (2019)

2. Usov, E.V., Butov, A.A., Chukhno, V.I.: Fuel Pin Melting in a Fast Reactor and Melt Solidification: Simulation Using the SAFR/V1 Module of the EVKLID/V2 Integral Code. Atomic Energy 124(3), 123–126 (2018)

3. Butov, A.A., Kamenskaya, D.D., Klimonov, I.A.: Simulation of melt behavior in the sodium-cooled reactor core catcher using the EUCLID/V2 integrated computer code HEFEST-FR module. Thermal Engineering 70(11), 5–13 (2023)

4. Saikina, T.A., Usov, E.V., Chukhno, V.I.: Validation of the Severe Accident Module of the EUCLIDE/V2 Integral Code on the Basis of Experiments on a Failure of Simulators of Single Fuel Rods and Fuel Assemblies. Thermal Engineering 70(4), 45–54 (2023)

5. Butov, A.A., Zhdanov, V.S., Klimonov, I.A.: Verification of the EUCLID/V2 Code Based on Experiments Involving Destruction of a Liquid Metal Cooled Reactor’s Core Components. Thermal Engineering 55(5), 16–24 (2019)