Zobrazeno 1 - 10
of 37
pro vyhledávání: '"S. Dawahra"'
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 9, Pp 1990-1997 (2020)
To support the safe operation of the Miniature Neutron Source Reactor (MNSR), a thermo-hydraulic transient model using the RELAP5/Mod3.2 code was simulated. The model was verified by comparing the results with the measured and the previously calculat
Externí odkaz:
https://doaj.org/article/82e367970a3c4454af8bb2b388ab6dfa
Publikováno v:
Results in Physics, Vol 11, Iss , Pp 564-569 (2018)
The study of core conversion of the IRT research reactor from the HEU to LEU fuels has been conducted in this paper. Fuel burnup, buildup of actinides and fission product inventory for the IRT research reactor with UO2-Al dispersion fuel for the vari
Externí odkaz:
https://doaj.org/article/8245fe9496a44136aa0f5bc05282b0c7
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 9, Pp 1990-1997 (2020)
To support the safe operation of the Miniature Neutron Source Reactor (MNSR), a thermo-hydraulic transient model using the RELAP5/Mod3.2 code was simulated. The model was verified by comparing the results with the measured and the previously calculat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::56b347255039bb9dff5f763286f85017
http://www.sciencedirect.com/science/article/pii/S1738573319308393
http://www.sciencedirect.com/science/article/pii/S1738573319308393
Publikováno v:
Results in Physics, Vol 11, Iss, Pp 564-569 (2018)
The study of core conversion of the IRT research reactor from the HEU to LEU fuels has been conducted in this paper. Fuel burnup, buildup of actinides and fission product inventory for the IRT research reactor with UO2-Al dispersion fuel for the vari
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d5f7a83df153df605cb4df11ca35a992
http://www.sciencedirect.com/science/article/pii/S2211379718316243
http://www.sciencedirect.com/science/article/pii/S2211379718316243
Autor:
S. Dawahra, Bassem Assfour
Publikováno v:
Annals of Nuclear Energy. 148:107730
In this work, the possibility of using nano-porous materials for the separation and storage of noble gases from the off-gas steam generated during the operation of nuclear reprocessing units was theoretically explored. To this end, simulations using
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f90fecfbc409cc43946cc2bcec2a20b4
https://doi.org/10.1016/j.anucene.2020.107730
https://doi.org/10.1016/j.anucene.2020.107730
Publikováno v:
Applied Radiation and Isotopes. 115:256-261
An effective modification to extend the maximum operation time of the Miniature Neutron Source Reactor (MNSR) to enhance the utilization of the reactor has been tested using the MCNP4C code. This modification consisted of inserting manually in each o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::dc672afad18d13bc7a4953ffc00630b5
https://doi.org/10.1016/j.apradiso.2016.06.031
https://doi.org/10.1016/j.apradiso.2016.06.031
Publikováno v:
Progress in Nuclear Energy. 88:28-32
Analysis of the Reactivity Temperature Coefficients of the Miniature Neutron Source Reactor (MNSR) for normal and accidental conditions (above 45 °C) using HEU-UAl4 and the LEU: U3Si, U3Si2 and U9Mo fuel were carried out in this paper. The Fuel Temp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::19d37a66e6df78f9a3ad4d6349767c40
https://doi.org/10.1016/j.pnucene.2015.11.012
https://doi.org/10.1016/j.pnucene.2015.11.012
Publikováno v:
Annals of Nuclear Energy. 85:1115-1118
A 3-D neutronic model for the 10 MW MTR research reactor has been conducted for the HEU (93%), MEU (45%) and LEU (20%) fuels using the MCNP4C code. This model has been used to study the effect of different types of reflector materials on the reactor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5f9de8b9e3ffdd3716de6c9d0160affe
https://doi.org/10.1016/j.anucene.2015.07.029
https://doi.org/10.1016/j.anucene.2015.07.029
Publikováno v:
Applied Radiation and Isotopes. 104:67-73
A comparative study for fuel conversion from the HEU to LEU in the Miniature Neutron Source Reactor (MNSR) has been performed in this paper using the MCNP4C code. The neutron energy and lethargy flux spectra in the first inner and outer irradiation s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f6db41e20a81447aed41d7238ebc0fd2
https://doi.org/10.1016/j.apradiso.2015.06.006
https://doi.org/10.1016/j.apradiso.2015.06.006
Publikováno v:
Progress in Nuclear Energy. 81:1-5
Calculations of the fuel burnup, core excess reactivity, and the reactivity worths of the top beryllium shim plates for two reflector types (beryllium and beryllium oxide (BeO)) in the Miniature Neutron Source Reactor (MNSR) have been presented in th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8d54be15f229ec409f9255ff5b5e0564
https://doi.org/10.1016/j.pnucene.2014.12.001
https://doi.org/10.1016/j.pnucene.2014.12.001