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Title: Protective structures on the surface of zirconium components of light water reactor cores: Formation, testing, and prototype equipment

The results of tests of plasma treatment of zirconium and deposition of protective yttrium coatings used as the methods of protection of zirconium components of light water reactor cores against hydrogenation are detailed. The amount of hydrogen in the treated sample exposed to superheated steam for 2500 h at temperature T = 400°C and pressure p = 1 atm was five times lower than the corresponding value for the untreated one. The amount of hydrogen in the sample coated with yttrium remained almost unchanged in 4000 h of exposure. A plasma method for rapid testing for hydrogen resistance is proposed. The hydrogenation rate provided by this method is 700 times higher than that in tests with superheated steam. The results of preliminary experiments confirm the possibility of constructing a unit for batch processing of the surfaces of fuel rod claddings.
Authors:
; ; ; ; ;  [1]
  1. National Research Nuclear University MEPhI (Moscow Engineering Physics Institute) (Russian Federation)
Publication Date:
OSTI Identifier:
22471874
Resource Type:
Journal Article
Resource Relation:
Journal Name: Physics of Atomic Nuclei; Journal Volume: 78; Journal Issue: 14; Other Information: Copyright (c) 2015 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CLADDING; COATINGS; FUEL RODS; HYDROGEN; HYDROGENATION; REACTOR SAFETY; SURFACES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YTTRIUM; ZIRCONIUM