Autor: Tenreiro, C. - Katalog OPAC zbiorów

Skocz do pozycji: 1.

Tytuł:: Study of heat transfer parameters on rhodium target for 103Pd production
Autorzy:: Sadeghi, M.
Tenreiro, C.
Van den Winkel, P.
Powiązania:: https://bibliotekanauki.pl/articles/148100.pdf
Data publikacji:: 2009
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: heat transfer
103Pd
rhodium
target
Opis:: The efficiency of cooling and the particle beam characteristics are important when high beam current irradiations are intended for production of radionuclides. The efficiency of cooling is determined by both the target carrier geometry and the flow rate of coolant, while the beam characteristics deal with the current density distribution on the irradiated surface area. Heat transfer on rhodium target to produce 103Pd via the 103Rh(p,n)103Pd reaction was investigated and the beam current was obtained more than 500 mi A.
Źródło:: Nukleonika; 2009, 54, 3; 169-173
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

Artykuł

Zmień widok

na półce

Skocz do pozycji: 2.

Tytuł:: Burn-up calculation of different thorium-based fuel matrixes in a thermal research reactor using MCNPX 2.6 code
Autorzy:: Gholamzadeh, Z.
Feghhi, S. A. H.
Soltani, L.
Rezazadeh, M
Tenreiro, C.
Joharifard, M.
Powiązania:: https://bibliotekanauki.pl/articles/148179.pdf
Data publikacji:: 2014
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: ThO2
neutronic parameters
fuel burn-up
233U
235U
239Pu fissile material
Opis:: Decrease of the economically accessible uranium resources and the inherent proliferation resistance of thorium fuel motivate its application in nuclear power systems. Estimation of the nuclear reactor’s neutronic parameters during different operational situations is of key importance for the safe operation of nuclear reactors. In the present research, thorium oxide fuel burn-up calculations for a demonstrative model of a heavy water- -cooled reactor have been performed using MCNPX 2.6 code. Neutronic parameters for three different thorium fuel matrices loaded separately in the modelled thermal core have been investigated. 233U, 235U and 239Pu isotopes have been used as fi ssile element in the thorium oxide fuel, separately. Burn-up of three different fuels has been calculated at 1 MW constant power. 135X and 149Sm concentration variations have been studied in the modelled core during 165 days burn-up. Burn-up of thorium oxide enriched with 233U resulted in the least 149Sm and 135Xe productions and net fi ssile production of 233U after 165 days. The negative fuel, coolant and void reactivity of the used fuel assures safe operation of the modelled thermal core containing (233U-Th) O2 matrix. Furthermore, utilisation of thorium breeder fuel demonstrates several advantages, such as good neutronic economy, 233U production and less production of long-lived α emitter high radiotoxic wastes in biological internal exposure point of view.
Źródło:: Nukleonika; 2014, 59, 4; 129-136
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

Artykuł

Zmień widok

na półce

Informacja

Wyszukujesz frazę "Tenreiro, C." wg kryterium: Autor

Źródło danych

Dostawca treści

Kolekcja

Rok wydania

Wydawca

Temat

Autor

Typ dokumentu

Język