Zobrazeno 1 - 4
of 4
pro vyhledávání: '"S. M. Mirvakili"'
Autor:
S. M. Mirvakili, C. Tenreiro, Zahra Alipoor, Zohreh Gholamzadeh, Seyed Amir Hossein Feghhi, H. Bagheri, M. Vahedi
Publikováno v:
Kerntechnik. 82:217-224
Thorium-based fuels could comprise several advantages and are being investigated as a potentially competitive option with uranium-based fuels for research or power reactors. The present study investigates computationally the application of two differ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c2594ab917b3a12c7c5ae4fc352ce79c
https://doi.org/10.3139/124.110636
https://doi.org/10.3139/124.110636
Publikováno v:
Kerntechnik. 80:263-269
Utilization of thorium-based fuel in different reactors has been under investigation for several decades. In fact, excellent breeding features, rather flattened distribution of power as well as proliferation resistance of such fuel cycle draws the at
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::170e22b578aaa02a883b8d13456f034e
https://doi.org/10.3139/124.110499
https://doi.org/10.3139/124.110499
Publikováno v:
Reliability Engineering & System Safety. 93:1377-1409
The main goal of this review paper is to analyze the total frequency of the core damage of the Iranian Heavy Water Research Reactor (IHWRR) compared with standard criteria and to determine the strengths and the weaknesses of the reactor safety system
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::86609a9e5b6a89d5fd0974a7f9118f02
https://doi.org/10.1016/j.ress.2007.10.002
https://doi.org/10.1016/j.ress.2007.10.002
Publikováno v:
Nuclear Power-System Simulations and Operation
In this chapter, we investigated an appropriate way to predict neutronics and thermalhydraulics parameters in a large scale VVER type nuclear reactors. A computer program is developed to automate this procedure using Artificial Neural Network (ANN) m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8dd5ade39612cd4b0b900f467b5f3504
http://www.intechopen.com/articles/show/title/a-literature-survey-of-neutronics-and-thermal-hydraulics-codes-for-investigating-reactor-core-parame
http://www.intechopen.com/articles/show/title/a-literature-survey-of-neutronics-and-thermal-hydraulics-codes-for-investigating-reactor-core-parame
