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Publications by S. Wexler

Tritium Retention in EBR-II-irradiated Boron Carbide

1974English

Related publications

Loading Diagrams of Experimental Subassemblies Irradiated in Ebr-Ii Runs 5 Through 42.

1970English

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 MaterialsAlloysCondensed Matter PhysicsMetals
2013English

EVALUATION OF THE EBR-II REACTOR-BUILDING ISOLATION SYSTEM. EBR-II Project.

1971English

CONCEPTUAL SYSTEM DESIGN DESCRIPTION OF THE EBR-II IN-CORE INSTRUMENT TEST FACILITY. EBR-II Project.

1969English

Diffusion/Desorption of Tritium From Irradiated Beryllium

Journal of Nuclear Materials
High Energy PhysicsMaterials ScienceEngineeringNuclear EnergyNuclear
1994English

Characterization of Pressureless Sintered Boron Carbide

2013English

Impact Scenarios in Boron Carbide: A Computational Study

Journal of Theoretical and Computational Chemistry
Computational TheoryComputer Science ApplicationsTheoretical ChemistryPhysicalMathematics
2016English

Atomic-Level Understanding of “Asymmetric Twins” in Boron Carbide

Physical Review Letters
AstronomyPhysics
2015English

Retention of Hydrogen Isotopes in Neutron Irradiated Tungsten

Materials Transactions
Mechanics of MaterialsMaterials ScienceCondensed Matter PhysicsMechanical Engineering
2013English

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