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Meeting Materials Science & Technology 2020
Symposium Ceramics in the Nuclear Fuel Cycle
Presentation Title Thermophysical Properties of Sintered Yttrium Dihydride
Author(s) Aditya P. Shivprasad, Vedant K Mehta, Joshua T. White, Michael W.D. Cooper, Tarik A. Saleh, Joseph R. Wermer, Erik P. Luther, Holly R. Trellue, D.V. Rao
On-Site Speaker (Planned) Aditya P. Shivprasad
Abstract Scope One current challenge to the nuclear industry is the ability to integrate nuclear energy with microgrids. Owing to their size, cost, and power output, microreactors could be designed to meet these needs. One such proposed microreactor design uses metal hydrides as the moderator due to their high hydrogen density, allowing enhanced fuel utilization and cost-effectiveness while keeping the core transportable. Yttrium dihydride is a promising candidate for this application due to its high thermal stability. Despite these advantages, it is difficult to produce YH2-x in geometries required for reactor design concepts. In this study, yttrium dihydride pellets were fabricated using powder metallurgical methods. Pellets were then analyzed for thermal diffusivity and heat capacity to determine thermal conductivity. Results will relate the thermophysical properties of the sintered pellets with those of hydrided monoliths in literature.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A First-principles Database Approach to Predicting Trans-Uranic Waste Forms
Evaluation of the Corrosion of High Purity CVD SiC in Light Water Reactor Environments
First-principles Study on the Trapping and Recombination of Tritium in Lithium Vacancy of the γ-LiAlO2 (100) Surface
Multi-scale Cs Sorbents Easily Transformable into Waste Confinement Matrices
Nb and Ti Alloying Effects on the Phase and Oxidation of U3Si2
Radiolytic Damage and Hydrogen Generation at Carbide – Water Interfaces
Thermophysical Properties of Sintered Yttrium Dihydride

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