Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Esmat H. Amin"'
Publikováno v:
Annals of Nuclear Energy. 109:385-395
One RIA accident, control rod ejection is a design basis accident for LWRs. Hence, it is a postulated event of very low probability, which would have serious consequences if not inherently accounted for in the design of the reactor and the safety sys
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b0375c74c7868165f231dc8034c32709
https://doi.org/10.1016/j.anucene.2017.05.029
https://doi.org/10.1016/j.anucene.2017.05.029
Publikováno v:
Arab Journal of Nuclear Sciences and Applications.
The feasibility of utilizing Thorium-Plutonium Mixed Oxide in the Westinghouse AP1000 Advanced Passive pressurized water reactor is examined under steady-state, beginning of life conditions. Initial core loading of the reactor has three types of UO2
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e6d7c841a0f2457bf515070cba4c4c21
https://doi.org/10.21608/ajnsa.2018.1892.1004
https://doi.org/10.21608/ajnsa.2018.1892.1004
Publikováno v:
Annals of Nuclear Energy. 80:70-76
Improving neutronic prediction is a very important step in designing advanced reactors and reactor fuel. There are three main critical reactor facilities of the CEA Cadarache. These reactor facilities are EOLE, MINERVE and MASURCA. The MINERVE reacto
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::74b870db526b91ac57f693e30c627259
https://doi.org/10.1016/j.anucene.2015.01.031
https://doi.org/10.1016/j.anucene.2015.01.031
Publikováno v:
International Journal of Nuclear Energy Science and Technology. 9:186
The study of the neutronic safety parameters in reactors is very important since it provides a guide for future study in reactor design. Also, it is considered as the basic step for reactor waste transmutation. In the present work, some of the basic
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::92ba38a2db06d3eeb33f5497f64ef2c6
https://doi.org/10.1504/ijnest.2015.071628
https://doi.org/10.1504/ijnest.2015.071628
Publikováno v:
International Journal of Nuclear Energy Science and Technology. 8:351
The calculation of integral parameters and power distribution is a very important task for fuel assembly design and whole core safety analysis. In this work, we used Monte Carlo (MCNP5) and deterministic lattice cell code WIMSD-5B with the diffusion
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::761a2523298de93359d0d241e357e8b0
https://doi.org/10.1504/ijnest.2014.064943
https://doi.org/10.1504/ijnest.2014.064943