Skeleton-creep based bubble growth model and multi-scale mechanical constitutive model for U-10Mo fuels under irradiation

X Jian, J Zhang, Y Li, S Ding - International Journal of Plasticity, 2023 - Elsevier
The macroscale irradiation swelling deformations of nuclear fuels induced by the solid and
gas fission products are one of the most concerned problems in nuclear reactor core design …

Modeling of irradiation-induced thermo-mechanical coupling and multi-scale behavior in a fully ceramic-microencapsulated fuel pellet

H Wei, J Zhang, Y Zhang, L Li, S Ding, Q Ren - Journal of Nuclear Materials, 2021 - Elsevier
Fully ceramic microencapsulated (FCM) fuels with enhanced accident tolerance can provide
an increased retention of fission products. In this study, a new method to model their …

Effects of the key parameters of TRISO particle buffer layer on in-pile thermo-mechanical behavior in FCM fuel pellets

H Wei, J Zhang, X Jian, Y Zhang, L Li, S Ding… - Journal of Nuclear …, 2021 - Elsevier
TRISO particle buffer layer is a critical functional part in FCM fuels. A skeleton stress model
for buffer layer is proposed, dependent on the current porosity, the maximum macroscale …

Investigation on the Irradiation-thermal–mechanical coupling behaviors of the solid Microencapsulated fuel rod

Q Deng, D Wang, S Li, J Cheng, X Ye… - Nuclear Engineering and …, 2023 - Elsevier
Abstract Solid Microencapsulated Fuel (SMF) is a kind of new accident-tolerant fuel (ATF),
where the TRISO coated fuel particles are dispersed directly into a type of matrix in the form …

[HTML][HTML] Effects of the mesostructures and irradiation conditions on the thermo-mechanical coupling behaviors in LWR-used fully ceramic-microencapsulated fuel …

H Wei, J Zhang, X Jian, Y Zhang, L Li, S Ding… - Nuclear Materials and …, 2023 - Elsevier
Fully ceramic microencapsulated (FCM TM) fuels, proposed as an accident tolerant fuel in
light water reactors (LWRs), consists of tri-structural isotropic (TRISO) fuel particles and …

Models for effective elastic constants of irradiated U-10Mo fuels with distributed fission gas bubbles

Y Li, G Ding, Z Xie, J Zhang, X Jian, S Ding… - Journal of Nuclear …, 2023 - Elsevier
The multi-scale related models for the effective elastic constants of porous U-10Mo fuels
under the irradiation conditions are developed with the proposed multi-level …

A new model of fission gas bubble growth and mechanism analysis for U-xZr fuels

X Mao, X Chen, X Jian, F Yan, S Ding - Journal of Nuclear Materials, 2025 - Elsevier
U-xZr alloys have a promising application prospect in advanced nuclear fuel elements, and
their macroscale volume growth under the extreme service environments are attracting more …

An improved volumetric growth model system and the corresponding computational method for porous carbon materials under irradiation

J Zhang, S Ding - Nuclear Engineering and Design, 2025 - Elsevier
Porous carbon layers within TRISO (TRistructural-ISOtropic) particles play an important role
in accommodating gaseous fission products and irradiation swelling of fuel kernels. In this …

Irradiation-condition dependent mechanisms controlling buffer densification and fracture in TRISO nuclear fuel particles

C Griesbach, T Gerczak, C McKinney, Y Zhang… - Journal of Nuclear …, 2025 - Elsevier
Designed to contain fission products during irradiation and off-normal accident scenarios,
tristructural isotropic (TRISO) particles are a robust fuel form consisting of a uranium …

Study on thermodynamic equivalent performance of fully ceramic microencapsulated fuel based on representative volume element model

C Yin, Z Xiao, K Zhang, P Cao, C Tang… - Frontiers in Energy …, 2024 - frontiersin.org
Fully ceramic microencapsulated (FCM) fuel is a five-layer intercalation system material
consisting of a UO2 core, a sparse pyrolytic carbon layer (Buffer), an inner dense pyrolytic …