A review of TRISO fuel performance models

JJ Powers, BD Wirth - Journal of Nuclear Materials, 2010 - Elsevier
Several advanced reactor designs incorporate tristructural isotropic (TRISO) fuel particles to
achieve high coolant temperature and high fuel burnup levels and thus require reliable and …

Numerical simulation of heat transfer in packed pebble beds: CFD-DEM coupled with particle thermal radiation

H Wu, N Gui, X Yang, J Tu, S Jiang - International Journal of Heat and Mass …, 2017 - Elsevier
Particle thermal radiation plays a significant role in many heat transport devices, such as
pebble-bed high temperature gas-cooled nuclear reactors (HTGR). The effect of particle …

CFD validation with optimized mesh using benchmarking data of pebble-bed high-temperature reactor

F Ahmed, N Ara, V Deshpande, AS Mollah… - Progress in Nuclear …, 2021 - Elsevier
In this study, a computational fluid dynamics (CFD) analysis conducted to predict the thermo-
hydraulic performance of the HTR-10, which is an experimental pebble bed reactor (PBR) …

A smoothed void fraction method for CFD-DEM simulation of packed pebble beds with particle thermal radiation

H Wu, N Gui, X Yang, J Tu, S Jiang - International Journal of Heat and Mass …, 2018 - Elsevier
The core of the high temperature gas-cooled reactor (HTGR) is a dense packed pebble bed
with large-sized fuel spheres. In the CFD-DEM simulations of fluid-particle systems on sub …

Microstructure and defect evolution of nuclear graphite under temperature-dependent ion irradiation

Y Zhao, S Lv, J Gao, Z Zhou, G Yeli, Z Li - Journal of Nuclear Materials, 2023 - Elsevier
Nuclear graphite plays a vital role in GEN-IV reactors and is expected to function in the
harsh environments such as high temperature and high-dose irradiation. The ion irradiation …

Optimum power determination and comparison of multi-pass and OTTO fuel management schemes of HTGR-based PeLUIt reactor

N Trianti, N Widiawati, C Wulandari, F Miftasani… - … Engineering and Design, 2023 - Elsevier
A co-generation reactor based on pebble-bed High-Temperature Gas-Cooled Reactor
(HTGR) has been designed. This study focuses on designing a modular nuclear reactor …

Neutron dose rate analysis on HTGR-10 reactor using Monte Carlo code

H Adrial, A Hamzah, S Bakhri… - Journal of Physics …, 2018 - iopscience.iop.org
The HTGR-10 reactor is cylinder-shaped core fuelled with kernel TRISO coated fuel particles
in the spherical pebble with helium cooling system. The outlet helium gas coolant …

[HTML][HTML] Optimization of the TRISO fuel particle distribution based on octahedral and icosahedral-based segmentation methods in the pebble-bed nuclear core

M Liu, C Zeng, Z Luo, H Gu, J Deng - International Journal of Advanced …, 2020 - Elsevier
The random distribution of TRISO fuel particles in the fuel elements may form local hotspots,
thereby increasing the thermal stress on TRISO particle layers that may cause particle …

Investigation on the oxidation behavior and multi-step reaction mechanism of nuclear graphite SNG742

W Lu, X Li, X Wu, L Sun, Z Li - Journal of Nuclear Science and …, 2020 - Taylor & Francis
Gas chromatography and numerical methods were used to investigate the oxidation
behavior of SNG742 nuclear grade graphite at 500–1100° C with different oxidizing gas flow …

[PDF][PDF] Analisis kuat sumber neutron dan perhitungan laju dosis neutron teras awal RDE

S Suwoto, H Adrial, Z Zuhair - … Jurnal Ilmiah Daur Bahan Bakar Nuklir, 2017 - academia.edu
AWAL RDE. Teras reaktor RDE (Reaktor Daya Eksperimental) berbentuk silinder non
anular, berbahan bakar kernel partikel berlapis TRISO yang berbentuk bola (pebble) dan …