A Functionally Graded Composite for Service in High-Temperature Lead- and Lead-Bismuth–Cooled Nuclear Reactors—I: Design
Author:
Affiliation:
1. Massachusetts Institute of Technology, H. H. Uhlig Corrosion Laboratory 185 Albany Street, Cambridge, Massachusetts 02139
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT12-A13481
Reference62 articles.
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2. A NEXT GENERATION SODIUM-COOLED FAST REACTOR CONCEPT AND ITS R&D PROGRAM
3. A thermal-fluid assessment of a cooled-vessel concept for a VHTR
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