Temat: neutronic analysis - Katalog OPAC zbiorów

Skocz do pozycji: 1.

Tytuł:: Neutronic analysis of nanofluids as a coolant in the Bushehr VVER - 1000 reactor
Autorzy:: Zarifi, E.
Jahanfarnia, G.
Veisy, F.
Powiązania:: https://bibliotekanauki.pl/articles/146618.pdf
Data publikacji:: 2012
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: nanofluids
neutronic analysis
VVER-1000
WIMS-D5
CITATION
Opis:: The main goal of this study was to perform the neutronic analysis of nanofluids as a coolant in reactor simulation. The variation of multiplication factor and thermal power have been investigated in the Bushehr VVER-1000 reactor core with using different nanofluids as coolant. In the applied analysis, water-based nanofluids containing various volume fractions of Al2O3, TiO2, CuO and Cu nanoparticles were used. The addition of different types and volume fractions of nanoparticles were found to have various effects on reactor neutronic characteristics. By using WIMS-D5 and CITATION code, the appropriate nanofluid with optimum volume percentage of nanoparticles was achieved. The results show that at low concentration (0.1% volume fraction) alumina is the optimum nanoparticle for normal reactor operation.
Źródło:: Nukleonika; 2012, 57, 3; 375-381
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

Artykuł

Skocz do pozycji: 2.

Tytuł:: RELAP5/MOD3 model and transient analyses for the MARIA research reactor in Poland
Autorzy:: Szczurek, J.
Czerski, P.
Bykowski, W.
Powiązania:: https://bibliotekanauki.pl/articles/147320.pdf
Data publikacji:: 2004
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: research reactor
transient analysis
neutronic parameters
qualification
Opis:: The RELAP5/MOD3 input data model of the MARIA research reactor has been developed to provide the capability for the analysis of the reactor core under loss of flow and reactivity insertion transients. The model was qualified against the reactor data at steady state conditions and, additionally, against the existing reliable experimental data for a transient initiated by the reactor scram. The results obtained with the code agree well with the experimental data. The RELAP transient simulation was performed for loss of forced flow accidents including two scenarios with protected and unprotected (no scram) reactor core. Calculations allow estimating time margin for reactor scram initiation and reactivity feedbacks contribution to the results. The presented input data model should be treated as the first step for developing of the model including the whole primary cooling circuit of the reactor.
Źródło:: Nukleonika; 2004, 49, 4; 149-157
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

Artykuł

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