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276,358 Matching Results

Start Over Resource Type Report Partner UNT Libraries Government Documents Department

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prev Results: 276,217 - 276,240 of 276,358 next
Best Match Title Creator Date Created (Newest) Date Created (Oldest) Date Added (Newest) Date Added (Oldest)
ZIRCALOY-2 PRESSURE TUBING. (open access)

ZIRCALOY-2 PRESSURE TUBING.

None
Date: January 1, 1968
Creator: Knecht, R. L. & Pankaskie, P. J.
System: The UNT Digital Library
Zircaloy-2 process tube activity, C Reactor (open access)

Zircaloy-2 process tube activity, C Reactor

This report presents the dose rates which were observed during the removal of a Zircaloy-2 process tube from C Reactor. The corresponding calculated activity is also presented for the purpose of correlation with the observed dose rate. The tube was removed on July 22, 1964, after having been irradiated by a neutron flux for 560 days (based on time operated efficiency). The tube activity was monitored with a super high range TP (0-5000 R/hr) by suspending a probe through an access port in the floor of the ``D`` machinery room. As tube 3353 was pushed and cut into sections, the highest activity observed was 675 R/hr, which was seen in the center three-foot segment. The corresponding calculated activity was 650 R/hr. The neutron flux profile, as shown by tube activities along its length, was extremely peaked in the center; for example, the area under the activity curve was less than one-third of the area under a cosine curve of the same amplitude and cycle length.
Date: August 26, 1964
Creator: Essig, T. H.
System: The UNT Digital Library
Zircaloy-2 Sheet and Strip Material (open access)

Zircaloy-2 Sheet and Strip Material

Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-2 Tubing for Fuel Sheathing (open access)

Zircaloy-2 Tubing for Fuel Sheathing

Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-2 Wire Material (open access)

Zircaloy-2 Wire Material

Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-4 Sheet and Strip Material (open access)

Zircaloy-4 Sheet and Strip Material

Scope. This specification covers Zircaloy-4 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-4 Tubing for Fuel Sheathing

Zircaloy-4 Tubing for Fuel Sheathing

Scope. This specification covers Zircaloy-4 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-4, Uranium Dioxide, and Materials Formed by Their Interaction. A Literature Review With Extrapolation of Physical Properties to High Temperatures. (open access)

Zircaloy-4, Uranium Dioxide, and Materials Formed by Their Interaction. A Literature Review With Extrapolation of Physical Properties to High Temperatures.

None
Date: January 1, 1967
Creator: Hammer, R. R.
System: The UNT Digital Library
Zircaloy-4 Wire Material (open access)

Zircaloy-4 Wire Material

Scope. This specification covers Zircaloy-4 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Final Report, November 1967--June 1971. (open access)

ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Final Report, November 1967--June 1971.

None
Date: January 1, 1971
Creator: Megerth, F. H.; Ruiz, C. P. & Wolff, U. E.
System: The UNT Digital Library
Zircaloy-Clad UO$sub 2$ Fuel Rod Evaluation Program. Progress Report No. 13, November 1970--March 1971. (open access)

Zircaloy-Clad UO$sub 2$ Fuel Rod Evaluation Program. Progress Report No. 13, November 1970--March 1971.

None
Date: January 1, 1971
Creator: Megerth, F. H.
System: The UNT Digital Library
Zircaloy-Clad UO$sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 1, November 1967--January 1968. (open access)

Zircaloy-Clad UO$sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 1, November 1967--January 1968.

None
Date: January 1, 1968
Creator: Megerth, F. H.
System: The UNT Digital Library
Zircaloy-Clad UO$sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 2, February 1968--April 1968. (open access)

Zircaloy-Clad UO$sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 2, February 1968--April 1968.

None
Date: January 1, 1968
Creator: Megerth, F. H.
System: The UNT Digital Library
ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 4, August--October 1968. (open access)

ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 4, August--October 1968.

None
Date: January 1, 1968
Creator: Megerth, F. H.
System: The UNT Digital Library
ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 5, November 1968--January 1969. (open access)

ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 5, November 1968--January 1969.

None
Date: January 1, 1969
Creator: Megerth, F. H.
System: The UNT Digital Library
Zircaloy-Clad UO$Sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 8, August--October 1969. (open access)

Zircaloy-Clad UO$Sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 8, August--October 1969.

None
Date: January 1, 1969
Creator: Megerth, F. H.
System: The UNT Digital Library
Zircaloy-Clad UO$sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 9, November 1969--January 1970. (open access)

Zircaloy-Clad UO$sub 2$ Fuel Rod Evaluation Program. Quarterly Progress Report No. 9, November 1969--January 1970.

None
Date: January 1, 1970
Creator: Megerth, F. H.
System: The UNT Digital Library
ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 10, February--April 1970. (open access)

ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 10, February--April 1970.

None
Date: January 1, 1970
Creator: Megerth, F. H.
System: The UNT Digital Library
ZIRCALOY--CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 11, May--July 1970. (open access)

ZIRCALOY--CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 11, May--July 1970.

None
Date: January 1, 1970
Creator: Megerth, F. H.
System: The UNT Digital Library
ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 12, August--October 1970. (open access)

ZIRCALOY-CLAD UO$sub 2$ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 12, August--October 1970.

None
Date: January 1, 1970
Creator: Megerth, F. H.
System: The UNT Digital Library
Zircaloy-Clad UO2 Fuel Rod Evaluation Program. Quarterly Progress Report Nos. 6 and 7, February--July 1969 (open access)

Zircaloy-Clad UO2 Fuel Rod Evaluation Program. Quarterly Progress Report Nos. 6 and 7, February--July 1969

None
Date: December 31, 1969
Creator: Megerth, F. H.
System: The UNT Digital Library
Zircaloy cladding performance under spent fuel disposal conditions; Progress report, May 1--October 31, 1989 (open access)

Zircaloy cladding performance under spent fuel disposal conditions; Progress report, May 1--October 31, 1989

The Brookhaven National Laboratory (BNL) Waste Materials and Environment Modeling (WMEM) Program has been assigned the task of helping the DOE formulate and certify analytical tools needed to support and/or strengthen the Waste Package Licensing Strategy. One objective of the WMEM program is to perform qualitative and quantitative analyses of irradiated Zircaloy cladding. This progress report presents the early findings of an on-going literature evaluation and the results of the numerical implementation of two models of Zircaloy creep. The report only addresses cladding degradation modes within intact, dry waste containers. Additional degradation modes will be considered when the study is expanded to include moist environments and partly failed containers. Further updates of the present analyses will also be provided.
Date: April 1, 1990
Creator: Pescatore, C.; Cowgill, M. G. & Sullivan, T. M.
System: The UNT Digital Library
Zircaloy Cladding Thickness Testers (open access)

Zircaloy Cladding Thickness Testers

Technical report. From Abstract : "A number of similar eddy current instruments were developed to measure the thickness of Zircaloy over uranium metal in the range of 5 to 25 mils, Zircaloy over UO2 in the range of 20 to 40 mils, and the wall thickness of Zircaloy tubes in the range of 20 to 40 mils. The instruments were designed for use with hand-held probes or with feeder-mounted probes to measure the inside and outside cladding thickness of tubular elements and the wall thickness of Zircaloy sheaths. The instruments have a sensitivity of 3 microamps per mil change in Zircaloy thickness and an accuracy of +/- mil."
Date: December 1961
Creator: Goodwin, Leslie E.
System: The UNT Digital Library
Zircaloy fuel cladding collapse test plan (open access)

Zircaloy fuel cladding collapse test plan

This test plan outlines the experimental philosophy and procedures for investigating the deformation behavior of Zircaloy fuel cladding under normal and near-normal reactor operating conditions. Such conditions impose compressive hoop and axial stresses on the cladding at temperatures that encompass the time-dependent or creep-strain regime. The purpose of the outlined study is to understand the deformation behavior of cladding under in- and out-of-reactor conditions so that mechanical properties correlations may be developed.
Date: August 1, 1976
Creator: Hobson, D. O.
System: The UNT Digital Library