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

Description: The purpose of this investigation is to determine the extent to which Zr and Zr alloys exhibit delayed failure (static fatigune) as caused by a combination of absorbed H and applied stress. Both notched and unnotched specimens of unalloyed Zr and Zircaloy-2 were hydrogenated to 200 ppm and 500 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture was observed which can be attributed to the delayed failure phenomenon; it… more
Date: March 30, 1962
Creator: Weinstein, D. & Holtz, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Materials Study. Research and Development of Metal Hydrides. Quarterly Report No. 4 for July 1, 1959 to September 30, 1959

Description: Activities during the period were directed primarily toward determination of the engineering properties of hydrided materials. The tensile strength and elongation, thermal expansion, thermal conductivity, and heat capacity of ZrH were determined as functions of temperature and H content. Preliminary results of Ti-base material studies indicate that these materials can be used for shielding and structural materials with the incorporation of rare earth hydrides. A summary of the work from Oct. l9… more
Date: October 30, 1959
Creator: Beck, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MOUND LABORATORY MONTHLY PROGRESS REPORT FOR MAY 1961 ON PLASTICS, RADIOELEMENTS, ISOTOPE SEPARATION, AND REACTOR FUELS

Description: tems were cast and cured. Results of chemical tests on aa epoxy curlang exudate are included. Comparison of solvent effects on retention of radioelements by stainless steel was started and data are tabulated for Ac/sup 227/, Th/sup 227/, a nd Ra/sup 22//sub 3/. Work on protactinium was resumed after suspension of this project in 1960. Methods for preparation of small quantities of highly enriched U isotopes are being examined. Included in the survey are chemical exchange, electromagnetic separa… more
Date: May 30, 1961
Creator: Eichelberger, J.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THERMAL CYCLING TESTS ON U-10 w/o Mo FOR THE ORNL FAST BURST REACTOR

Description: One of the uncertainties concerning the use of uranium-10 wt.% molybdenum in the ORNL Fast Burst Reactor is the thermal-cycling behavior of this alloy. Accordingly, an experimental program was undertaken to determine whether transformation or distortion of gamma-phase uranium--10 wt.% molybdenum can occur during simulated fast-burstreactor thermal cycling, and, should transformation occur, to establish the thermal cycling behavior of partially transformed uranium- - 10 wt.% molybdenum. Specimen… more
Date: July 30, 1960
Creator: Minushkin, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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On the Mechanism of Yielding and Flow in Iron

Description: The activation energy, activation volume, snd frequency factor were evaluated for yielding (delay time for yielding, upper yield stress, lower yield stress, and Luders band propagation) and flow (friction stress, flow stress, and dislocation mobility) for various irons and steels from data in the literature. It was found that the values of these flow parameters and their stress dependence were the same, within experimental error, for both yielding and flow, and for all the materials considered.… more
Date: May 30, 1961
Creator: Conrad, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium metallography

Description: From international metallography society symposium on speciment preparation for metallography; Los Angeles, California, USA (23 Sep 1973). An evaluation of the effectiveness of plutonium metallography reveals inadequacies in electrolysis preparation techniques. The probable causes and the approaches to the problems that have been proposed by the participating laboratories over the past two decades are reviewed. A brief history of the metal is included. (auth)
Date: April 30, 1974
Creator: Cramer, E.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Post-operational examinations of two carbide-fueled in-pile converters

Description: 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 … more
Date: September 30, 1970
Creator: Yang, L.; Horner, M. H. & Cochran, F. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plate-shape voids in neutron irradiated boron carbide

Description: From symposium on pore structures and properties of materials; Prague, Czechoslovakia (18 Sep 1973). Several processes are known to produce lattice vacancies in sufficient excess of the thermal equilibrium concentration that they precipitate out as voids. In the case of certain nuclear transmutations, a solid solution of gas is simultaneously produced at a concentration corresponding to a high equilibrium pressure and, if this gas diffuses into the voids, the equilibrium shape for the void is a… more
Date: April 30, 1974
Creator: Ashbee, K.H.G. & DuBose, C.K.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Status of uranium nitride development program at the Oak Ridge National Laboratory. Part II

Description: From RDT/SNS meeting on materials development for space reactor power systems; Washington, D. C. (23 Apr 1968). Declassified 26 Nov 1973. Information is included on encapsulated UN irradiation testing in the Materials Testing Reactor, results of post-irradiation evaluation of UN capsules, and irradiation testing of clad UN fuel pins in the Low Intensity Test Reactor and in the Oak Ridge Research Reactor. (JRD)
Date: April 30, 1974
Creator: Weaver, S.C. & Scott, J.L. (comps.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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New etch for liquid metal fast breeder reactor materials

Description: From 6th meeting of International Metallographic Society of America; Los Angeles, California, USA (25 Sep 1973). Preparation and performance of an etchant composed of 10 ml HCl, 10 ml HBr, and 1 ml of HF for fuel and cladding is reported. Results of application of this etchant to irradiated UO/sub 2/-PuO/sub 2/ fuel specimens, stainless steels, and lncoloy 800 are described. (JRD)
Date: April 30, 1974
Creator: Bender, J.H.; Baker, C. & Johnson, K.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Category-C: Materials Data Nuclear Subsystem, E-105 Appendix. Volume III

Description: To aid in the handling of these Category C Materials Data, they are bound in six volumes: Volumes 1 through 6. Volume 6 contains the confidential-Restricted Data. The complete listing of the DRMs contained in these six volumes are delineated in the Table of Contents according to DRM No., and the corresponding Materials covered in each volume. Each unclassified volume contains a complete Table of Contents for the five volumes.
Date: April 30, 1975
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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