Effect of water chemistry on the erosion-corrosion of aluminum in high temperature high velocity water (open access)

Effect of water chemistry on the erosion-corrosion of aluminum in high temperature high velocity water

This paper reports on a laboratory study of erosion-corrosion on aluminum surfaces in high temperature water. It is essentially a continuation of a similar previous study with refinement in testing procedure and the addition of electrochemical measurements to study the phenomenon. The electrochemical procedures are of intrinsic worth, because such measurements have never before been conducted with such an unusual cell geometry as imposed by the erosion-corrosion testing apparatus.
Date: January 30, 1970
Creator: Jones, D. A.
Object Type: Report
System: The UNT Digital Library
Half-plant low dichromate evaluation at KW Reactor: Production Test-176. Final report (open access)

Half-plant low dichromate evaluation at KW Reactor: Production Test-176. Final report

This final report details production test-176, the primary purpose of which was to provide a quantitative comparison of fuel element 8001 aluminum alloy cladding corrosion in cooling water containing 0.5 and 1.0 ppm sodium dichromate inhibitor. Secondary purposes were to provide information on cladding corrosion as a function of temperature and as a function of time at both inhibitor concentrations. The primary purpose was well fulfilled: Equations were developed to describe and predict fuel element weight losses at both dichromate concentrations and the effect of dichromate concentration on localized corrosion was clearly established. Little effect of dichromate concentration on localized corrosion was observed when fuel cladding temperatures were below 115--120 C but above these temperatures the localized corrosion definitely was more severe in coolant containing 0.5 ppm inhibitor. The bottom rows of fuel element supports rapidly corroded away at the higher temperatures which caused a further increase in local temperatures due to flow imbalances and this in turn accelerated the localized corrosion. Because the higher dichromate concentration reduced the amount of support corrosion, 1.0 ppm dichromate should be employed to control localized corrosion whenever cladding temperatures are expected to be above 120 C for long periods of time. These tests …
Date: September 30, 1970
Creator: Larrick, A. P.
Object Type: Report
System: The UNT Digital Library
K$sup -$p $Yields$ $Sigma$$sup +-$$pi$$sup -+$ BETWEEN 1730 MeV AND 2150 MeV. (open access)

K$sup -$p $Yields$ $Sigma$$sup +-$$pi$$sup -+$ BETWEEN 1730 MeV AND 2150 MeV.

None
Date: August 30, 1970
Creator: Kane, D.; Birge, R. W.; Ely, Jr., R. P.; Hoven, J.; Kalmus, G. E. & Van Horn, A.
Object Type: Article
System: The UNT Digital Library
Materials properties data book. Volume 1-A. Nickel-base alloys, refractory metals, other nonferrous metals (open access)

Materials properties data book. Volume 1-A. Nickel-base alloys, refractory metals, other nonferrous metals

None
Date: August 30, 1970
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Post-operational examinations of two carbide-fueled in-pile converters (open access)

Post-operational examinations of two carbide-fueled in-pile converters

Two 90UC--10ZrC fueled converters, IC-13 of Mark VI configuration and IC- C3 of Mark VIIB configuration, were examined in hot cell after in-pile operation. IC-3 operated for 4395 hours at an average emitter temperature of 1675 deg C as a converter test and then for 2945 hours at an average emitter temperature of ~1500 deg C as a fuel irradiation test; the average fuel burnup achieved was 2.5 x 10/ sup 20/ fission/c.c. IC-C3 operated 5445 hours at an average emitter temperature of 1670 deg C as a converter test; the average fuel burnup achieved was 5 x 10/ sup 19/ fission/c.c. The carbide fuel contained 4 wt % tungsten and had a C/U atom ratio of 1.05. Other unique features for the converter components were fluoride tungsten claddings of controlled fluorine contents (18 ppM for IC-I3 and 19 ppM for IC-C3), and the presence of a high temperature seal and a graphite sorption cesium reservoir in IC-C3 converter. The results obtained on fuel swelling, emitter deformation, fuel-cladding interaction and microstructures of various converter components are presented. Solutions to the problem areas encountered are recommended. (auth)
Date: September 30, 1970
Creator: Yang, L.; Horner, M. H. & Cochran, F. L.
Object Type: Report
System: The UNT Digital Library
Advanced direct-radiating thermoelectric program. Final report (open access)

Advanced direct-radiating thermoelectric program. Final report

The purpose of this report is to help achieve the overall program goals for the development of thermo-electric modules to be incorporated in reactor or isotope space-vehicle power systems, a series of design objectives was specified.
Date: May 30, 1970
Creator: Johnson, J. L. & Garvey, L. P.
Object Type: Report
System: The UNT Digital Library
Radiation effects on electronics. Preliminary guidelines for designing electronics for operation in a radiation environment, s110-XCE01-W181 (open access)

Radiation effects on electronics. Preliminary guidelines for designing electronics for operation in a radiation environment, s110-XCE01-W181

None
Date: September 30, 1970
Creator: Messenger, G. C. & Stadig, J. E.
Object Type: Report
System: The UNT Digital Library
Materials properties data book. Volume I. Introduction and light metals (open access)

Materials properties data book. Volume I. Introduction and light metals

None
Date: August 30, 1970
Creator: unknown
Object Type: Report
System: The UNT Digital Library
High-temperature nuclear heat source study (open access)

High-temperature nuclear heat source study

None
Date: December 30, 1970
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Materials properties data book. Volume III. Nonmetallics and appendices (open access)

Materials properties data book. Volume III. Nonmetallics and appendices

None
Date: August 30, 1970
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Effects of irradiation on hydrided zirconium--uranium alloy NAA 120-4 experiment (open access)

Effects of irradiation on hydrided zirconium--uranium alloy NAA 120-4 experiment

None
Date: June 30, 1970
Creator: Davies, N. F. & Forrester, R. E.
Object Type: Report
System: The UNT Digital Library
Materials properties data book. Volume II. Ferrous alloys (open access)

Materials properties data book. Volume II. Ferrous alloys

None
Date: August 30, 1970
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Richland O2 R&D program, annual report, summary (open access)

Richland O2 R&D program, annual report, summary

The complete annual R & D report consists of this summary and two companion reports, one from DUN which covers reactors and another from ARHCO which covers separations. These companion reports are listed in the set of references in the back of this summary.
Date: June 30, 1970
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Lung Scanning With /sup 99m/Tc Ferric Hydroxide Macroaggregates. (open access)

Lung Scanning With /sup 99m/Tc Ferric Hydroxide Macroaggregates.

None
Date: April 30, 1970
Creator: Yano, Y.; Anger, H. O.; McRae, J. & Honbo, D.
Object Type: Article
System: The UNT Digital Library
SNAP-23A PROGRAM, PHASES 1 AND 2. THERMOELECTRIC CONVERTER DEVELOPMENT PROGRAM. Quarterly Report No. 13, January 1, 1970--March 31, 1970. (open access)

SNAP-23A PROGRAM, PHASES 1 AND 2. THERMOELECTRIC CONVERTER DEVELOPMENT PROGRAM. Quarterly Report No. 13, January 1, 1970--March 31, 1970.

None
Date: April 30, 1970
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Process specifications and standards for the 1970 thorium campaign in the Purex Plant (open access)

Process specifications and standards for the 1970 thorium campaign in the Purex Plant

The process specifications and standards for thorium processing operations in the Purex Plant are presented. These specifications represent currently known limits within which plant processing conditions must be maintained to meet defined product requirements safely and with minimum effect on equipment service life. These specifications cover the general areas of feed, essential materials, and chemical hazards. (LK)
Date: June 30, 1970
Creator: Van der Cook, R.E. & Ritter, G.L.
Object Type: Report
System: The UNT Digital Library
Generator-Produced /sup 81m/Kr for Dynamic Studies of the Lungs and Heart With the Scintillation Camera. (open access)

Generator-Produced /sup 81m/Kr for Dynamic Studies of the Lungs and Heart With the Scintillation Camera.

None
Date: April 30, 1970
Creator: Yano, Y.; McRae, J. & Anger, H. O.
Object Type: Article
System: The UNT Digital Library
SNAP-23A PROGRAM: THERMOELECTRIC CONVERTER DEVELOPMENT PROGRAM. Final Report. (open access)

SNAP-23A PROGRAM: THERMOELECTRIC CONVERTER DEVELOPMENT PROGRAM. Final Report.

None
Date: December 30, 1970
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Investigation of Mixed Conduction in Solid Electrolytes. Progress Report, December 1, 1970--November 30, 1971. (open access)

Investigation of Mixed Conduction in Solid Electrolytes. Progress Report, December 1, 1970--November 30, 1971.

None
Date: September 30, 1970
Creator: Rapp, R. A.
Object Type: Report
System: The UNT Digital Library
E-1 CAM Revision 4 (open access)

E-1 CAM Revision 4

this report is a descriptive journey of the E-1 CAM Revision 4
Date: April 30, 1970
Creator: unknown
Object Type: Report
System: The UNT Digital Library