Publications

Argibay, Nicolas A.; Lu, Ping L.; Chandross, M.; Furnish, Timothy A.; Boyce, Brad B.; O'Brien, Christopher J.; Adams, David P.; Clark, Blythe C.; Nordquist, Christopher N.; Rodriguez, Mark A.; Dugger, Michael T.; Grine, Alejandro J.; Nation, Brendan L.

Abstract not provided.

Argibay, Nicolas A.; Lu, Ping L.; Chandross, M.; Furnish, Timothy A.; Boyce, Brad B.; Foiles, Stephen M.; Adams, David P.; Clark, Blythe C.; O'Brien, Christopher J.; Rodriguez, Mark A.; Dugger, Michael T.; Abdeljawad, Fadi F.; Nation, Brendan L.

Abstract not provided.

Boyce, Brad B.; Bufford, Daniel C.; Hattar, Khalid M.; Mook, William M.; Sharon, John A.; Furnish, Timothy A.; Foiles, Stephen M.; Clark, Blythe C.; Abdeljawad, Fadi F.; O'Brien, Christopher J.

Abstract not provided.

O'Brien, Christopher J.; Clark, Blythe C.; Foiles, Stephen M.

Abstract not provided.

Boyce, Brad B.; Foiles, Stephen M.; Hattar, Khalid M.; Clark, Blythe C.; Abdeljawad, Fadi F.; Bufford, Daniel C.; Furnish, Timothy A.; O'Brien, Christopher J.

Abstract not provided.

Boyce, Brad B.; Foiles, Stephen M.; Hattar, Khalid M.; Clark, Blythe C.; Abdeljawad, Fadi F.; Bufford, Daniel C.; Furnish, Timothy A.; O'Brien, Christopher J.

Abstract not provided.

Tikare, Veena T.; Weck, Philippe F.; Schultz, Peter A.; Clark, Blythe C.

This report documents the development, demonstration and validation of a mesoscale, microstructural evolution model for simulation of zirconium hydride {delta}-ZrH{sub 1.5} precipitation in the cladding of used nuclear fuels that may occur during long-term dry storage. While the Zr-based claddings are manufactured free of any hydrogen, they absorb hydrogen during service, in the reactor by a process commonly termed ‘hydrogen pick-up’. The precipitation and growth of zirconium hydrides during dry storage is one of the most likely fuel rod integrity failure mechanisms either by embrittlement or delayed hydride cracking of the cladding. While the phenomenon is well documented and identified as a potential key failure mechanism during long-term dry storage (NUREG/CR-7116), the ability to actually predict the formation of hydrides is poor. The model being documented in this work is a computational capability for the prediction of hydride formation in different claddings of used nuclear fuels. This work supports the Used Fuel Disposition Research and Development Campaign in assessing the structural engineering performance of the cladding during and after long-term dry storage. This document demonstrates a basic hydride precipitation model that is built on a recently developed hybrid Potts-phase field model that combines elements of Potts-Monte Carlo and the phase-field models. The model capabilities are demonstrated along with the incorporation of the starting microstructure, thermodynamics of the Zr-H system and the hydride formation mechanism.