Monte Carlo burnup in HTR system with various TRISO packing
PBN-AR
Instytucja
Wydział Energetyki i Paliw (Akademia Górniczo-Hutnicza im. Stanisława Staszica w Krakowie)
Informacje podstawowe
Główny język publikacji
EN
Czasopismo
Annals of Nuclear Energy
ISSN
0306-4549
EISSN
1873-2100
Wydawca
Pergamon-Elsevier Science Ltd.
Rok publikacji
2016
Numer zeszytu
Strony od-do
419--430
Numer tomu
92
Link do pełnego tekstu
Identyfikator DOI
Liczba arkuszy
0.85
Autorzy
Słowa kluczowe
EN
Monte Carlo
HTR
depletion
TRISO
nuclear fuel
fuel lattice
Streszczenia
Język
EN
Treść
Monte Carlo codes allow for the calculation of precise representation of complex HTR geometry including the double heterogeneity of a fuel. Various approaches to coated fuel particles (TRISO) placement can be applied and the impact on criticality calculations have been already assessed by several authors. Because static neutron transport simulations are affected by different fuel lattice modeling, it can be expected that the systematic discrepancies should appear during burnup calculation as well. In this paper we compare the impact of different TRISO placement and packing factor in the model on the results of the depletion simulation. For numerical tests we chose simplified model of the fuel block from High Temperature Reactor of prismatic type and the continuous energy Monte Carlo burnup code MCB5. Burnup dependent discrepancies of kinf and nuclide concentrations have been successfully observed. Five arrangement models of fuel kernels have been compared in our work: cuboidal lattice truncated by fuel rod, cubic and hexagonal lattices without rod truncation, cubic lattice with stochastic geometry option and rod filled with one layer of randomly located particles. We put emphasis on the constant mass of fuel kernels in the system and correlate obtained results with physical and statistical aspects of TRISO packing so as to explain observed discrepancies.
Cechy publikacji
original article
peer-reviewed
Inne
System-identifier
idp:097419
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