Amanote Research
Register
Sign In
Discover open access scientific publications
Search, annotate, share and cite publications
Publications by S. Wexler
Tritium Retention in EBR-II-irradiated Boron Carbide
Related publications
Loading Diagrams of Experimental Subassemblies Irradiated in Ebr-Ii Runs 5 Through 42.
Characterization of Irradiated Metal Waste From the Pyrometallurgical Treatment of Used EBR-II Fuel
Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science
Mechanics of Materials
Alloys
Condensed Matter Physics
Metals
EVALUATION OF THE EBR-II REACTOR-BUILDING ISOLATION SYSTEM. EBR-II Project.
CONCEPTUAL SYSTEM DESIGN DESCRIPTION OF THE EBR-II IN-CORE INSTRUMENT TEST FACILITY. EBR-II Project.
Diffusion/Desorption of Tritium From Irradiated Beryllium
Journal of Nuclear Materials
High Energy Physics
Materials Science
Engineering
Nuclear Energy
Nuclear
Characterization of Pressureless Sintered Boron Carbide
Impact Scenarios in Boron Carbide: A Computational Study
Journal of Theoretical and Computational Chemistry
Computational Theory
Computer Science Applications
Theoretical Chemistry
Physical
Mathematics
Atomic-Level Understanding of “Asymmetric Twins” in Boron Carbide
Physical Review Letters
Astronomy
Physics
Retention of Hydrogen Isotopes in Neutron Irradiated Tungsten
Materials Transactions
Mechanics of Materials
Materials Science
Condensed Matter Physics
Mechanical Engineering