Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Amer A. Al Qaaod"'
Publikováno v:
Radiation Protection Dosimetry. 199:572-579
In 2020, the ICRU released a new report which includes the re-definition of the operational quantities used in radiation protection and new conversion coefficients from physical quantities to operational radiation protection quantities. An assessment
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2ea8f1b82c8558ea680f262ef4513333
https://doi.org/10.1093/rpd/ncad046
https://doi.org/10.1093/rpd/ncad046
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 35, Iss 4, Pp 294-303 (2020)
In this paper, the feasibility of high-level radioactive waste transmutation in accelerator driven system sub-critical reactor assembly, has been studied for two zone's model and with three different core configurations. The inner zone has a fast neu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::af8c40af70544151dbe2890d630c4663
https://doi.org/10.2298/ntrp2004294q
https://doi.org/10.2298/ntrp2004294q
Autor:
Amer A. Al Qaaod, Volodymyr Gulik
Publikováno v:
Nuclear Science and Techniques. 31
This study aims to produce 229Th using an innovative nuclear reactor concept, i.e., accelerator-driven system (ADS) reactor. Herein, we investigated the feasibility of producing 229Th from neutron transmutation of 226Ra to expand the availability of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f08c78bfa8159221e01dc9925592c3c4
https://doi.org/10.1007/s41365-020-00753-2
https://doi.org/10.1007/s41365-020-00753-2
Publikováno v:
EPJ Web of Conferences. 261:02004
The neutron reference field produced by a heavy-water moderated 252Cf source is used at PTB for calibrating neutron-measuring devices. Knowledge of the precise neutron spectrum is very important for the investigation of operational radiation protecti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b3429915db31769b756928c8d11efa2
https://doi.org/10.1051/epjconf/202226102004
https://doi.org/10.1051/epjconf/202226102004
Publikováno v:
Annals of Nuclear Energy. 121:101-107
For long times there has been a sustained international interest in partitioning and transmutation of spent fuel produced by fission reactors, in particular both plutonium (Pu) and minor actinides (MA), which are associated with nuclear proliferation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e85dd47894321898ce4cc1b2b1334b5b
https://doi.org/10.1016/j.anucene.2018.07.012
https://doi.org/10.1016/j.anucene.2018.07.012
Publikováno v:
Applied Radiation and Isotopes. 167:109410
Radon and progeny concentration measurements in various drink samples are intrinsically important for assessing the health risks resulting from daily consumption of these drinks. In this study the comparison between two Solid State Nuclear Track Dete
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ca67fb0962eb0edac7cc88705de48db4
https://doi.org/10.1016/j.apradiso.2020.109410
https://doi.org/10.1016/j.apradiso.2020.109410
Publikováno v:
Annals of Nuclear Energy. 94:332-337
Plutonium (Pu) and minor actinides (MAs) are responsible for the majority of radiotoxicity, heat generation, and proliferation risk of nuclear spent fuel. Accelerator driven system (ADS) reactors can employ Pu and MA for transmutation and power gener
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ed6958d2d36a7924d0276e8cef729a94
https://doi.org/10.1016/j.anucene.2016.03.016
https://doi.org/10.1016/j.anucene.2016.03.016
Publikováno v:
Annals of Nuclear Energy. 81:336-341
The accelerator driven system (ADS) is a very interesting option to improve the safety of nuclear power reactor and for transmutation of spent fuel. The Texas phase of the reactor–accelerator coupling experiment (RACE), completed in March 2006, dem
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::413043b3d84138964d460ef7101e183b
https://doi.org/10.1016/j.anucene.2015.03.013
https://doi.org/10.1016/j.anucene.2015.03.013
Publikováno v:
Journal of Physics: Conference Series. 1253:012028
In the present study, the fast spectrum transmutation experimental facility (FASTEF) core that considered for the MYRRHA reactor is modelled using Monte Carlo MCNPX code. The effect of changing the type of material and radius of the cylindrical targe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6a67bb6a56a5572169b659cb581e58e2
https://doi.org/10.1088/1742-6596/1253/1/012028
https://doi.org/10.1088/1742-6596/1253/1/012028
Autor:
Amer A. Al Qaaod
Publikováno v:
Journal of Medical Imaging and Radiation Sciences. 50:S16
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e929970b1c8f1705624cb4eaaf3ab83d
https://doi.org/10.1016/j.jmir.2019.03.053
https://doi.org/10.1016/j.jmir.2019.03.053