Thermomechanical process optimization of U-10wt% Mo – Part 2: The effect of homogenization on the mechanical properties and microstructure-Reference-Cited by-同舟云学术

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Thermomechanical process optimization of U-10wt% Mo – Part 2: The effect of homogenization on the mechanical properties and microstructure

Published:2015-10 Issue: Volume:465 Page:710-718
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Joshi Vineet V.,Nyberg Eric A.,Lavender Curt A.,Paxton Dean,Burkes Douglas E.

Funder

U.S. Department of Energy

National Nuclear Security Administration

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference14 articles.

1. The Fuel fabrication capability and uranium-molybdenum alloy: an overview;Burkes,2014

2. Overview of LANL progress in process development, advanced characterization methods and prototype fabrication;Dombrowski,2012

3. Finite element analysis of the rolling of u10mo alloy: parametric study on rolling process parameters;Soulami,2014

4. Development and Properties of Uranium-base Alloys Resistant to Corrosion in High-temperature Water;McGeary,1955

5. Uranium Alloys for High-temperature Application;Saller,1955

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1. A European manufacturing line for monolithic U–Mo bare foil production;Nuclear Engineering and Design;2024-06

2. Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development;Journal of Nuclear Engineering and Radiation Science;2024-04-17

3. Minimizing thickness variation in monolithic U-10Mo fuel foil and Zr interlayer during hot rolling: A microstructure-based finite element method analysis;Materials Today Communications;2022-08

4. Mechanical and Thermophysical properties of low enriched uranium-10wt% molybdenum rolled foils;Journal of Nuclear Materials;2022-05

5. The role of second phase particles and grain boundaries on recrystallization: Quasi-in situ experiments and modeling in U-10Mo alloy system;Journal of Nuclear Materials;2022-02

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