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Publications by W.J. Gray
K-Basin Spent Nuclear Fuel Characterization Data Report
Constant-Stress Irradiation Creep Experiments on Graphite.
HIGH-TEMPERATURE GRAPHITE IRRADIATIONS: 550 TO 1450$sup 0$C.
Interactive Leach Tests of UO/sub 2/ and Spent Fuel With Waste Package Components in Salt Brine
Related publications
Reactive Behavior of K-Basin Spent Nuclear Fuel
Spent Nuclear Fuel Effective Thermal Conductivity Report
Interim Report Spent Nuclear Fuel Retrieval System Fuel Handling Development Testing
Spent Nuclear Fuel Canister Storage Building Conceptual Design Report
Using X-Ray, K-Edge Densitometry in Spent Fuel Characterization
K Basin Fuel Characterization Program Technical Baseline Summary
Spent Nuclear Fuel Project Stage and Store K Basin SNF in Canister Storage Building Functions and Requirements. Revision 1
Data Compilation Report: Gas and Liquid Samples From K West Basin Fuel Storage Canisters
Spent Nuclear Fuel Cold Vacuum Drying Facility Comprehensive Formal Design Review Report