Fission Gas and Bias‐Driven Swelling of Nuclear Fuels

Abstract

The article contains sections titled: Introduction Behavior of Gaseous Fission Products for Normal Reactor Conditions Gaseous Fission Product Behavior Nucleation and Growth of Intragranular Fission Gas Bubbles Intergranular Fission Gas: Grain Faces and Edges Bubble Interlinkage Intra‐ and Intergranular Bubble Swelling Fuel Element Swelling Solid Fission Product Swelling Fission Gas Swelling at Low Temperature/Low Burnup Fission Gas Swelling at Low Temperature/High Burnup Fission Gas Swelling at High Temperature Fission Gas Release Grain Size Effects on Gas Release Validation of FASTGRASS Model for Fission‐Gas Release DART : Dispersion Analysis Research Tool Mechanical Model Mechanical Model with Aluminide Formation DART Calculational Algorithms DART Validation Cavitational Swelling of α‐Uranium Zone in U–Pu–Zr Fuel Comparison with Data from U–10Zr and U–19Pu–10Zr Fuel Elements Behavior of Fission Products under Reactor Transient Conditions Prediction of Fuel Ductility under Transient Heating Microcracking Grain Growth/Grain‐Boundary Sweeping Mobility of Fission Gas Bubbles under Transient Conditions Fission Gas Release during Transient Conditions Modeling the Behavior of Volatile Fission Products ( VFPs ) VFP Chemistry VFP Release under Normal Operating Conditions VFP Release during Transient Heating Effect of Fuel Heating Rate on VFP Release Effect of Fuel Burnup on VFP Release Effect of Fuel Irradiation Temperature on VFP Release Effect of Cesium Chemistry on VFP Release Fission Gas Behavior in Amorphous Nuclear Fuels Model of Amorphous Fuel Bubble Growth at the Knee Bubble Growth after the Knee‐Point Comparison with Data Example of a Calculated Fuel Property Introduction Viscosity Model for Binary Alloys Undergoing Amorphization Looking Forward