The results of effective irradiation swelling in a wide range of burnup levels are numerically obtained for an inert matrix fuel, which are verified with DART model. The fission gas swelling of fuel particles is calculated with a mechanistic model, which depends on the external hydrostatic pressure. Additionally, irradiation and thermal creep effects are included in the inert matrix. The effects of matrix creep strains, external hydrostatic pressure and temperature on the effective irradiation swelling are investigated. The research results indicate that (1) the above effects are coupled with each other; (2) the matrix creep effects at high temperatures should be involved; and (3) ranged from 0 to 300 MPa, a remarkable dependence of externa...
The goal of this deliverable is to present a synthesis of the model developments achieved during the...
The low temperature matrix swelling of UO2-fuels was analysed as a function of burn-up, taking into ...
The harsh conditions in the reactor affect the thermal and mechanical performance of the fuel plate ...
Under irradiation, dispersion nuclear fuel meat consists of a three-phase composite of fuel particle...
The Dispersion Analysis Research Tool (DART) contains models for fission-gas induced fuel swelling, ...
An integrated model is developed for analysing the coupled and stress-dependent phenomena of fission...
This report describes the primary physical models that form the basis of the DART mechanistic comput...
A physics-based model is developed for analysing the coupled phenomena of fission gas swelling and r...
Monolithic UMo fuels have a higher uranium density than previously developed fuels. They have become...
The irradiation creep–swelling interaction parameters were precisely derived for Monju fuel pin clad...
A mathematical model has been developed for estimati the burnup at which mechanical failure occurs i...
Fission of actinides from nuclear waste in inert matrices (materials without uranium) can reduce the...
Access restricted to the OSU CommunityA computer model for the simulation of long-term, steady-state...
International audienceThis paper presents the state-of-the-art knowledge about the micro-mechanical ...
In the first part of the paper, experimental results for the Xe depletion in the matrix of high burn...
The goal of this deliverable is to present a synthesis of the model developments achieved during the...
The low temperature matrix swelling of UO2-fuels was analysed as a function of burn-up, taking into ...
The harsh conditions in the reactor affect the thermal and mechanical performance of the fuel plate ...
Under irradiation, dispersion nuclear fuel meat consists of a three-phase composite of fuel particle...
The Dispersion Analysis Research Tool (DART) contains models for fission-gas induced fuel swelling, ...
An integrated model is developed for analysing the coupled and stress-dependent phenomena of fission...
This report describes the primary physical models that form the basis of the DART mechanistic comput...
A physics-based model is developed for analysing the coupled phenomena of fission gas swelling and r...
Monolithic UMo fuels have a higher uranium density than previously developed fuels. They have become...
The irradiation creep–swelling interaction parameters were precisely derived for Monju fuel pin clad...
A mathematical model has been developed for estimati the burnup at which mechanical failure occurs i...
Fission of actinides from nuclear waste in inert matrices (materials without uranium) can reduce the...
Access restricted to the OSU CommunityA computer model for the simulation of long-term, steady-state...
International audienceThis paper presents the state-of-the-art knowledge about the micro-mechanical ...
In the first part of the paper, experimental results for the Xe depletion in the matrix of high burn...
The goal of this deliverable is to present a synthesis of the model developments achieved during the...
The low temperature matrix swelling of UO2-fuels was analysed as a function of burn-up, taking into ...
The harsh conditions in the reactor affect the thermal and mechanical performance of the fuel plate ...