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Wyświetlanie 1-2 z 2
Tytuł:
Production of 166Ho and 153Sm using hot atom reactions in neutron irradiated tris(cyclopentadienyl) compounds
Autorzy:
Nassan, L.
Achkar, B.
Yassine, T.
Powiązania:
https://bibliotekanauki.pl/articles/147591.pdf
Data publikacji:
2011
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
hot atom reactions
holmium-166
miniature nuclear source reactor (MNSR)
Opis:
The behavior of a recoiled 166Ho and 153Sm resulting from the reactions 165Ho(n,gamma)166Ho and 152Sm(n,gamma)153Sm in the organometallic compounds tris(cyclopentadienyl)holmium (C5H5)3Ho(III), and tris(cyclopentadienyl)samarium (C5H5)3Sm(III) were investigated. Several chemical separation methods were developed for each compound to separate the recoil products from the irradiated compound. Retention value of 0.2 �} 0.1% was obtained for (C5H5)3Ho(III) using sublimation. Another value of retention of 0.4 plus or minus 0.1% resulted when column chromatography was used. Paper chromatography (using Whatman Chr. 1 and Whatman Chr. 4) gave different retention values of about 0.11 plus or minus 0.05%, and 0.4 plus or minus 0.1%, respectively. Similar behavior of 153Sm in irradiated (C5H5)3Sm(III) was found when paper chromatography was used for separation. The different retention values given by different methods of separation were discussed. An important improvement of the specific activity was achieved as compared with other published results in this field. The obtained results pointed out that tris(cyclopentadienyl)holmium and samarium could be used to produce high specific activity of 166Ho and 153Sm in the Syrian low flux miniature nuclear source reactor (MNSR), where the averaged achieved enrichment factor for holmium compound was found to be greater than 1.6 x 107.
Źródło:
Nukleonika; 2011, 56, 4; 263-267
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Neutronic analysis for core conversion (HEU–LEU) of the low power research reactor using the MCNP4C code
Autorzy:
Aldawahra, S.
Khattab, K.
Gorge, S.
Powiązania:
https://bibliotekanauki.pl/articles/971506.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
MNSR reactor
HEU fuel
LEU fuel
MCNP4C code
safety parameters
Opis:
Comparative studies for conversion of the fuel from HEU to LEU in the miniature neutron source reactor (MNSR) have been performed using the MCNP4C code. The HEU fuel (UAl4-Al, 90% enriched with Al clad) and LEU (UO2 12.6% enriched with zircaloy-4 alloy clad) cores have been analyzed in this study. The existing HEU core of MNSR was analyzed to validate the neutronic model of reactor, while the LEU core was studied to prove the possibility of fuel conversion of the existing HEU core. The proposed LEU core contained the same number of fuel pins as the HEU core. All other structure materials and dimensions of HEU and LEU cores were the same except the increase in the radius of control rod material from 0.195 to 0.205 cm and keeping the outer diameter of the control rod unchanged in the LEU core. The effective multiplication factor (κ eff), excess reactivity (ρ ex), control rod worth (CRW), shutdown margin (SDM), safety reactivity factor (SRF), delayed neutron fraction (β eff) and the neutron fl uxes in the irradiation tubes for the existing and the potential LEU fuel were investigated. The results showed that the safety parameters and the neutron fl uxes in the irradiation tubes of the LEU fuels were in good agreements with the HEU results. Therefore, the LEU fuel was validated to be a suitable choice for fuel conversion of the MNSR in the future.
Źródło:
Nukleonika; 2015, 60, 2; 367-371
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
    Wyświetlanie 1-2 z 2

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