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Catalog of Technical Reports

Catalog of Technical Reports
Author: United States. Dept. of Commerce. Office of Technical Services
Publisher:
Total Pages: 850
Release:
Genre:
ISBN:

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Nuclear Science Abstracts

Nuclear Science Abstracts
Author:
Publisher:
Total Pages: 938
Release: 1976-03
Genre: Nuclear energy
ISBN:

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Influence of Chemical Composition on Uniform Corrosion of Zirconium-Base Alloys in Autoclave Tests

Influence of Chemical Composition on Uniform Corrosion of Zirconium-Base Alloys in Autoclave Tests
Author: CM. Eucken
Publisher:
Total Pages: 15
Release: 1989
Genre: Chemical effects
ISBN:

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The influence of the composition of Zircaloy-type alloys has been evaluated previously with respect to mechanical properties (1973 International Conference Zirconium in the Nuclear Industry, ASTM STP 551) and to nodular corrosion (1985 International ASTM Conference on Zirconium in the Nuclear Industry, ASTM STP 939). The present study extends this previous work to include uniform corrosion, which is of interest for cladding tubes and spacer grids of fuel assemblies. A variety of ingots with compositions both within and outside of the ASTM specification range for Zircaloy-2 and Zircaloy-4 have been tested. The material was fabricated into strips using a conventional fabrication procedure, which incorporated an intermediate beta quench followed by working and annealing in the upper alpha-range. The alloy elements covered the following ranges: tin: 0.2 to 1.7%; iron: 0.05 to 0.53%; chromium: 0.04 to 1.05%; and nickel: 0.003 to 0.046%. In addition, oxygen, carbon, silicon, and phosphorus were varied over the range of standard Zircaloy contents.


TID.

TID.
Author:
Publisher:
Total Pages: 252
Release: 19??
Genre: Energy development
ISBN:

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An Innovative Ceramic Corrosion Protection System for Zircaloy Cladding

An Innovative Ceramic Corrosion Protection System for Zircaloy Cladding
Author:
Publisher:
Total Pages: 5
Release: 2003
Genre:
ISBN:

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Light Water reactor (LWR) fuel performance is currently limited by thermal, chemical and mechanical constraints associated with the design, fabrication, and operation of the fuel in incore operation. Corrosion of the zirconium based (Zircaloy-4) alloy cladding of the fuel is a primary limiting factor. Recent success at the University of Florida in developing thin ceramic films with great adhesive properties for metal substrates offers an innovative breakthrough for eliminating a major weakness of the Zircaloy clad.?The University of Florida proposes to coat the existing Zircaloy clad tubes with a ceramic coating for corrosion protection. An added bonus of this approach would be the implementation of a boron-containing burnable poison outer layer will also be demonstrated as part of the ceramic coating development. In this proposed effort, emphasis will be on the ceramic coating with only demonstration of feasibility on the burnable outer coating approach. This proposed program i s expected to give a step change (approximately a doubling) in clad lifetime before failure due to corrosion. In the development of ceramic coatings for Zircaloy-4 clad, silicon carbide and zirconium carbide coatings will first be applied to Zircaloy-4 coupons and cladding samples by thermal assisted chemical vapor deposition, plasma assisted chemical vapor deposition or by laser ablation deposition. All of these processes are in use at the University of Florida and have shown great potential. The questions of adhesion and thermal expansion mismatch of the ceramic coating to the Zircaloy substrate will be addressed. Several solutions to these conditions will be examined, if needed. These solutions include the use of a zirconium oxide compliant layer, employment of a laser roughened surface and the use of a gradient composition interlayer. These solutions have already been shown to be effective for other high modulus coatings on metal substrates. Mechanical properties and adhesion of the coatings will be monitored as a function of the coating process parameters. The corrosion protection of the various coatings will be evaluated by accelerated corrosion testing. Engineering requirements for coating a full size Zircaloy clad tube will be determined. It is expected that the coating process will add approximately 10 dollars or 10% to the price of a tube. In the second approach, the University of Florida will demonstrate the feasibility to add a boron carbide outer layer to functions as a burnable poison.(B204).


Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry
Author: George P. Sabol
Publisher: ASTM International
Total Pages: 953
Release: 2000
Genre: Microstructure
ISBN: 0803124996

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