Fission gas behaviors and relevant phenomena in different nuclear fuels: a review of models and experiments

J Guo, H Lai, W Zhou, J Wei - Frontiers in Energy Research, 2022 - frontiersin.org
Reactor structural integrity and nuclear safety are seriously affected by the fission gas
behaviors and relevant physical phenomena in nuclear fuels. In this review, the fission gas …

Finite element based fuel performance investigation of U3Si2–FeCrAl design under normal and RIA conditions

C Deng, Y He, F **ang, Y Wu, J Zhang, W Tian… - Progress in Nuclear …, 2022 - Elsevier
U 3 Si 2–FeCrAl system has been a promising Accident Tolerant Fuels (ATFs) candidate for
its higher thermal conductivity, higher uranium density and lower oxidation rate. As a part of …

Thermal diffusivity and thermal conductivity of SiC composite tubes: the effects of microstructure and irradiation

T Koyanagi, H Wang, CM Petrie, CP Deck… - Journal of Nuclear …, 2021 - Elsevier
Cladding thermal conductivity is an important physical property in assessing the
performance of silicon carbide (SiC)-cladded fuels for nuclear reactors. However, there is a …

Numerical study of flow and heat transfer characteristics in a simplified dual fluid reactor

H Elgendy, K Czerski - Energies, 2023 - mdpi.com
This study presents the design and computational fluid dynamics (CFD) analysis of a mini
demonstrator for a dual fluid reactor (DFR). The DFR is a novel concept currently under …

Assessing the effect of some ATF materials and uncertainties on their properties under normal operation conditions by means of the TRANSURANUS code

P Van Uffelen, A Schubert, Z Soti - Proceedings of the 23rd Pacific Basin …, 2023 - Springer
In this work, we present the first implementation of U3Si2 fuel properties in the
TRANSURANUS code. Following the short overview of the implemented fuel properties, we …

Effects of graphene dispersion in hot pressing UO2-graphene nanosheet ceramic matrix composites

Y Wang, Z He, J Yang, X Ye, C Yu, S Qiu, L Yao… - Ceramics …, 2022 - Elsevier
The safe use of nuclear energy is crucial, especially after the Fukushima nuclear disaster. A
novel uranium dioxide (UO 2)-graphene nanosheet (GN) ceramic matrix composite fuel has …

An assessment of UO2 and ATF concept fuel performance modeling demands against current experimental capabilities under LOCA conditions

A Probert, J Watson, A Aitkaliyeva - Annals of Nuclear Energy, 2024 - Elsevier
This paper compiles and digitizes the publicly reported data for integral loss of coolant
accident (LOCA) testing so it can be used by both multiphysics modeling and simulation …

Annular fuel behavior analysis of U3Si2 fuel and FeCrAl cladding based on multiphysics field method

M Liu, R Liu, S Liu - Progress in Nuclear Energy, 2024 - Elsevier
Safety, efficiency and economic benefits cannot be ignored in the development of nuclear
energy. As a type of widely used fuel in nuclear reactors, solid fuel has limited potential, long …

Surface and size effects on the behaviors of point defects in irradiated crystalline solids

A Ozturk, M Gencturk, K Ahmed - Frontiers in Materials, 2021 - frontiersin.org
We present an elaborate study of the surface and size effects on the transient and steady-
state behaviors of point defects in irradiated solids. In this investigation, both pure Ni and …

Transient testing of uranium silicide fuel in zircaloy and silicon carbide cladding

D Kamerman, N Woolstenhulme, D Imholte… - Annals of Nuclear …, 2021 - Elsevier
Using the newly restarted Transient Reactor Test (TREAT) facility at Idaho National
Laboratories, fresh (unirradiated) U 3 Si 2 fuel pellets were tested under reactivity-initiated …