The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor-Reference-Cited by-同舟云学术

The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor

Published:2019-05 Issue:5 Volume:66 Page:293-301
ISSN:0040-6015
Container-title:Thermal Engineering
language:en
Short-container-title:Therm. Eng.

Author:

Butov A. A.,Zhdanov V. S.,Klimonov I. A.,Kudashov I. G.,Kutlimetov A. E.,Mosunova N. A.,Strizhov V. F.,Sorokin A. A.,Frolov S. A.,Usov E. V.,Chukhno V. I.

Publisher

Pleiades Publishing Ltd

Subject

Energy Engineering and Power Technology,Nuclear Energy and Engineering

Link

http://link.springer.com/content/pdf/10.1134/S0040601519050021.pdf

Reference26 articles.

1. N. A. Mosunova, “The EUCLID/V1 integrated code for safety assessment of liquid metal cooled fast reactors. Part 1: Basic models,” Therm. Eng. 65, 304–316 (2018). https://doi.org/10.1134/S0040601518050063

2. V. M. Alipchenkov, A. V. Boldyrev, D. P. Veprev, Yu. A. Zeigarnik, P. V. Kolobaeva, E. V. Moiseenko, N. A. Mosunova, E. F. Seleznev, V. F. Strizhov, E. V. Usov, S. L. Osipov, V. S. Gorbunov, D. A. Afremov, and A. A. Semchenkov, “The EUCLID/V1 integrated code for safety assessment of liquid metal cooled fast reactors. Part 2: Validation and verification,” Therm. Eng. 65, 627–640 (2018). https://doi.org/10.1134/S004060151809001X

3. V. M. Alipchenkov, A. M. Anfimov, D. A. Afremov, V. S. Gorbunov, Yu. A. Zeigarnik, A. V. Kudryavtsev, S. L. Osipov, N. A. Mosunova, V. F. Strizhov, and E. V. Usov, “Fundamentals, current state of the development of, and prospects for further improvement of the new-generation thermal-hydraulic computational HYDRA-IBRAE/LM code for simulation of fast reactor systems,” Therm. Eng. 63, 130–139 (2016). https://doi.org/10.1134/S0040601516020014

4. E. V. Usov, A. A. Butov, V. I. Chukhno, I. A. Klimonov, I. G. Kudashov, V. S. Zhdanov, N. A. Pribaturin, N. A. Mosunova, V. F. Strizhov, Fuel Pin Melting in a Fast Reactor and Melt Solidification: Simulation Using the SAFR/V1 Module of the EVKLID/V2 Integral Code. Atomic Energy. 2018, v. 124, i. 3, pp. 147–153. https://doi.org/10.1007/s1051201803892

5. E. V. Usov, A. A. Butov, V. I. Chukhno, I. A. Klimonov, I. G. Kudashov, V. S. Zhdanov, N. A. Pribaturin, N. A. Mosunova, V.F. Strizhov. SAFR/V1 (EVKLID/V2 Integral Code Module) Aided Simulation of Melt Movement Along the Surface of a Fuel Element in a Fast Reactor During a Serious Accident. Atomic Energy, 2018, v. 124, i. 4, pp. 232–237. https://doi.org/10.1007/s1051201803892

Cited by 16 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. 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;Atomic Energy;2024-08-21

2. Application of the EUCLID Integrated Code’s HYDRA-IBRAE/LM Thermal Hydraulic Module for Analyzing the Steam Generators of Sodium Cooled Reactor Plants;Thermal Engineering;2023-12

3. Requirements for the EUCLID-F Integral Code for the Deterministic Analysis of Accidents in Fusion Reactors;Physics of Atomic Nuclei;2023-12

4. Simulation of Melt Behavior in the Sodium-Cooled Reactor Core Catcher Using the EUCLID/V2 Integrated Computer Code HEFEST-FR Module;Thermal Engineering;2023-11

5. Validation of the Severe Accident Module of the EUCLID/V2 Integral Code on the Basis of Experiments on a Failure of Simulators of Single Fuel Rods and Fuel Assemblies;Thermal Engineering;2023-04