Temat: HTR - Katalog OPAC zbiorów

Skocz do pozycji: 1.

Tytuł:: Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel
Autorzy:: Oettingen, Mikołaj
Cetnar, Jerzy
Powiązania:: https://bibliotekanauki.pl/articles/2055669.pdf
Data publikacji:: 2021
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: HTR
homogenization
thorium
Monte Carlo
Opis:: The volumetric homogenization method for the simplified modelling of modular high-temperature gas-cooled reactor core with thorium-uranium fuel is presented in the paper. The method significantly reduces the complexity of the 3D numerical model. Hence, the computation time associated with the time-consuming Monte Carlo modelling of neutron transport is considerably reduced. Example results comprise the time evolutions of the effective neutron multiplication factor and fissionable isotopes (233U, 235U, 239Pu, 241Pu) for a few configurations of the initial reactor core.
Źródło:: Nukleonika; 2021, 66, 4; 133--138
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 2.

Tytuł:: Monte Carlo analysis of the battery-type high temperature gas cooled reactor
Autorzy:: Grodzki, M.
Darnowski, P.
Niewiński, G.
Powiązania:: https://bibliotekanauki.pl/articles/240584.pdf
Data publikacji:: 2017
Wydawca:: Polska Akademia Nauk. Czytelnia Czasopism PAN
Tematy:: HTGR
HTR
Monte Carlo
serpent
U-battery
SMR
battery type
wąż
bateria
rodzaj
Opis:: The paper presents a neutronic analysis of the battery-type 20 MWth high-temperature gas cooled reactor. The developed reactor model is based on the publicly available data being an ‘early design’ variant of the U-battery. The investigated core is a battery type small modular reactor, graphite moderated, uranium fueled, prismatic, helium cooled high-temperature gas cooled reactor with graphite reflector. The two core alternative designs were investigated. The first has a central reflector and 30×4 prismatic fuel blocks and the second has no central reflector and 37×4 blocks. The SERPENT Monte Carlo reactor physics computer code, with ENDF and JEFF nuclear data libraries, was applied. Several nuclear design static criticality calculations were performed and compared with available reference results. The analysis covered the single assembly models and full core simulations for two geometry models: homogenous and heterogenous (explicit). A sensitivity analysis of the reflector graphite density was performed. An acceptable agreement between calculations and reference design was obtained. All calculations were performed for the fresh core state.
Źródło:: Archives of Thermodynamics; 2017, 38, 4; 209--227
1231-0956
2083-6023
Pojawia się w:: Archives of Thermodynamics
Dostawca treści:: Biblioteka Nauki

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