Zobrazeno 1 - 4
of 4
pro vyhledávání: '"I. D. Abdelrazek"'
Publikováno v:
Kerntechnik. 80:32-39
The present work was developed within the frame of the IAEA Coordinated Research Project 1496 “Innovative methods in research reactor analysis: Benchmark against experimental data on neutronics and thermal-hydraulic computational methods and tools
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1e4ead84e6d8bb4e5626f1810319d194
https://doi.org/10.3139/124.110475
https://doi.org/10.3139/124.110475
Publikováno v:
Annals of Nuclear Energy. 70:36-43
The present work is developed within the frame of the IAEA Coordinated Research Program 1496, “Innovative methods in research reactor analysis: Benchmark against experimental data on neutronics and thermal-hydraulic computational methods and tools
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b478c538b4e2753ac04f678694197d8a
https://doi.org/10.1016/j.anucene.2014.02.023
https://doi.org/10.1016/j.anucene.2014.02.023
Publikováno v:
Kerntechnik. 75:97-102
A computation code THERMOHYD has been developed to perform the steady state thermal-hydraulic calculations of the MTR type research reactors fueled with plate-type-fuel, in the ranges of pressures and temperatures typical for MTR reactors. The code c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::35f411299605aaf80859c0685bf417e4
https://doi.org/10.3139/124.110068
https://doi.org/10.3139/124.110068
Publikováno v:
Kerntechnik. 69:116-121
A steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor has been performed using the computer code TERMIC. The analysis has included both, the verification of the core design as well as the performance of the equilibrium core. The u
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7a98cd6b13e691021a895f501fe8f263
https://doi.org/10.3139/124.100198
https://doi.org/10.3139/124.100198