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Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Description: Zirconium-based alloys Zircaloy-2 and Zircaloy-4 are widely used in the nuclear industry as cladding materials for light water reactor (LWR) fuels. These materials display a very good combination of properties such as low neutron absorption, creep behavior, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion and/or oxidation, especially in the case of Zircaloy-4. However, over the last couple of years, in the post-Fukushima Daiichi world, energetic efforts have been undertaken to improve fuel clad oxidation resistance during off-normal temperature excursions. Efforts have also been made to improve upon the already achieved levels of mechanical behavior and reduce hydrogen uptake. In order to facilitate the development of such novel materials, it is very important to achieve not only engineering control, but also a scientific understanding of the underlying material degradation mechanisms, both in working conditions and in storage of used nuclear fuel. This report strives to contribute to these efforts by constructing the thermodynamic models of both alloys; constructing of the respective phase diagrams, and oxidation mechanisms. A special emphasis was placed upon the role of zirconium suboxides in hydrogen uptake reduction and the atomic mechanisms of oxidation. To that end, computational thermodynamics calculations were conducted concurrently with first-principles atomistic modeling.
Date: August 1, 2013
Creator: Glazoff, Michael V.
Partner: UNT Libraries Government Documents Department

EURATOM PROGRAM "Improved Zirconium Alloys"

Description: Introduction: "This report is an expanded version of the regular monthly letter report and is prepared in this form with the intention of reviewing work on the subject program for Euratom technical personnel. Work performed during the month of September, which normally constitutes the entire letter report, has been condensed under one heading."
Date: October 5, 1960
Creator: Weinstein, Daniel. & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : Ninth Monthly Report Covering the Period December 1 to December 31, 1960

Description: The following report is the ninth in a series of monthly reports covering the program with the objective of developing alloys having superior 680 F water and/or 750 to 900 F steam corrosion resistance, as well as developing higher strength alloys for current temperature ranges while still maintaining corrosion resistance comparable to that of Zircaloy-2. This report was made covering the period December 1 to December 31, 1960.
Date: January 5, 1961
Creator: Weinstein, Daniel. & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : Quarterly Report, July 1, 1962 - September 30, 1962

Description: The following report is one of a series of quarterly reports following the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between July 1 to September 30, 1962 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: October 12, 1962
Creator: Weinstein, Daniel. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : Quarterly Report, July 1, 1961 - September 30, 1961

Description: The following report is one of a series of quarterly reports following the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between July 1 to September 30, 1961.
Date: October 16, 1961
Creator: Weinstein, Daniel. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : A Summary of Recent Work in This Field (Interim Report)

Description: Abstract: "As part of a program entitled "Improved Zirconium Alloys" a brief summary of a present zirconium research at various organizations has been prepared. Information was obtained by telephone and personnel contact; and these discussions, along with the organization and personnel, are presented."
Date: November 8, 1960
Creator: Weinstein, Daniel. & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : Quarterly Report, April 1, 1961 - June 30, 1961

Description: This report is part of a series of quarterly reports following the progression of determining an improved zirconium alloy for service in superheated water and steam. Within this report--covering the period of April 1, 1961 to June 30, 1961--approximately 75 compositions have already been prepared prior, and presently are being arc-melted and fabricated into corrosion specimens. This document continues the investigations of the effect of zirconium purity and heat treatment on corrosion and resistance.
Date: July 11, 1961
Creator: Weinstein, Daniel. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : Quarterly Report, April 1, 1962 - June 30, 1962

Description: The following report is part of a series of quarterly reports discussing investigations on the development of zirconium-base alloys having corrosion resistance and strength superior to Zircaloy-2 and/or development of materials of equivalent corrosion resistance by exhibiting enhanced strength. This report covers the period between May 29 and June 18 of 1958, made by the United States and the European Atomic Energy Community (EURATOM).
Date: July 13, 1962
Creator: Weinstein, Daniel. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : Twelfth Monthly Report, April 1, 1961 - April 30, 1961

Description: The following report is the twelfth of a series of quarterly reports following the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between April 1 to April 31, 1961 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: May 4, 1961
Creator: Weinstein, Daniel. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : Summary Report, April 1, 1960 - January 31, 1961

Description: Abstract: "The objectives of this program are the development of zirconium-base alloys possessing exceptionally good corrosion resistance to 680 F water or 750-900 F system and/or improved strength at elevated temperatures. Approximately 100 binary compositions were prepared and screened by corrosion testing in 680 F water; selected compositions were exposed to 750 F steam. The data obtained indicate promising bases for ternary and quaternary alloys. Related investigations involving zirconium purity and heat treatment for improvement of corrosion properties are proceeding. Hydrogen pickup and mechanical properties will be used as acceptability tests on promising compositions."
Date: February 28, 1961
Creator: Weinstein, Daniel.; Holtz, F. C. & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : Technical Progress Report, February 1, 1961 - February 28, 1962

Description: The following report is one of a series of quarterly reports following the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between February 1, 1961 to February 28, 1962 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: February 28, 1962
Creator: Weinstein, Daniel. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : Quarterly Report, October 1, 1960 - December 31, 1960

Description: The following report is one of a series of quarterly reports following the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between October 1 to December 31, 1960 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: February 2, 1961
Creator: Weinstein, Daniel.; Holtz, F. C. & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department

Improved Zirconium Alloys : Quarterly Report, October 1, 1961 - December 31, 1961

Description: The following report is one of a series of quarterly reports following the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between October 1 to December 31, 1961 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: January 12, 1962
Creator: Weinstein, Daniel. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department

Delayed Failure Hydrogen Embrittlement of Zirconium : Quarterly Report no. 1, September 15, 1961 to December 14, 1961

Description: Abstract: "The purpose of this investigation is to determine the extent to which zirconium exhibits delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress. Both notched and unnotched specimens of unalloyed zirconium and Zircaloy-2 are being initially hydrogenated to 200 ppm by means of a modified Sieverts apparatus, and delayed failure studies are proceeding at room-temperature. Thus far only preliminary data on unnotched, unalloyed zirconium are available; at the 200 ppm hydrogen level, this material appears to be relatively insensitive to delayed failure at room-temperature."
Date: January 3, 1962
Creator: Weinstein, Daniel. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department

Delayed Failure Hydrogen Embrittlement of Zirconium : Quarterly Report No. 2, December 15, 1961 to March 14, 1962

Description: Abstract: "The purpose of this investigation is to determine the extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress. Both notched and unnotched specimens of unalloyed zirconium and Zircaloy-2 have been hydrogenated to 200 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture has been observed which can be attributed to the delayed failure phenomenon; it appears that these materials are relatively insensitive to static fatigue. The effects of grain size, temperature, cold deformation, and superheated water and steam corrosion on susceptibility to delayed failure are being determined."
Date: March 30, 1962
Creator: Weinstein, Daniel. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department

Delayed Failure Hydrogen Embrittlement of Zirconium : Quarterly Report No. 3, March 15, 1962 to June 14, 1962

Description: The following report is the third Quarterly Report in a series whose investigative purpose is to determine the extent to which zirconium and zirconium alloys exhibit delayed failure as caused by a combination of absorbed hydrogen and applied stress.
Date: June 6, 1962
Creator: Weinstein, Daniel. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department