Interpretation of High-Burnup Fuel Annealing Tests
スポンサーリンク
概要
- 論文の詳細を見る
The growth of the porosity in high-burnup fuel is of particular interest when considering the effect of fission gas retention within the high-burnup structure (HBS). A mechanistic model of porosity growth under annealing conditions for light water reactor (LWR) UO2 fuel with typical stereological parameters of the HBS has been developed. The model takes into account both multipore and surface interactions that lead to fission gas release from the HBS porosity. We have applied the model to an HBS annealing experiment and found that reasonable agreement with the experimental gas release curve can be achieved for a vacancy diffusion enthalpy close to that measured experimentally. A comparison of the model behaviours at different pore growth rates is performed. We found that the model exhibits porosity evolution characteristics independent of the growth rate, specifically the existence of a maximum porosity, a continuous gas release, and a decreasing pore number density. A general comparison between the model results and in-pile data indicates that up to 250 MWd/kgU, most of the gas is retained within the HBS.
著者
-
Chawla Rakesh
Paul Scherrer Institut
-
BLAIR Paul
Paul Scherrer Institut
-
KHVOSTOV Grigori
Paul Scherrer Institut
-
ROMANO Antonino
ENUSA Industrias Avanzadas, S.A.
-
HELLWIG Christian
Nordostschweizerische Kraftwerke AG (NOK) Kernenergie
関連論文
- Experimental Validation of Reaction Rate Distributions for a SVEA-96+ BWR Assembly with Hafnium Control Blades
- Experimental Validation of Channel Bowing Effects on Pin Power Distributions in a Westinghouse SVEA-96+ Assembly
- Comparisons of Deterministic Neutronic Calculations with Monte Carlo Results for an Advanced BWR Fuel Assembly with Hafnium Control Blades
- The Effect of Nuclear Data on the MCNPX Modeling of Moderator Level Variations in the CROCUS Critical Facility
- Investigation of ADS-Type Heterogeneities in the MUSE4 Critical Configuration
- Application and In-depth Assessment of RETRAN-3D for Best Estimate Analysis of Nuclear Power Plant Transients
- Interpretation of High-Burnup Fuel Annealing Tests
- Statistical Uncertainty Analysis Applied to Fuel Depletion Calculations
- The Effect of Nuclear Data on the MCNPX Modeling of Moderator Level Variations in the CROCUS Critical Facility