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Elastic Thermal Stress in Reactor Fuel Elements -- a Comparative Study of Various Shapes

Description: A method for comparison and evaluation of thermoelastic stresses is given for a range of fuel element shapes based on parameters available from the initial study of a reactor system. The shapes studied, in descending order of stress level are circular rods, concentric tubes, flat plates, and a matrix of circular holes.
Date: August 1962
Creator: Binns, Ian M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary Hazards Report on Enriched Fuel Element Loading for the BNL Research Reactor

Description: Report issued by the Brookhaven National Laboratory discussing a hazards report on replacing the research center's current fuel elements with new highly enriched elements. As stated in the introduction, "this report is a summary of the studies, both theoretical and experimental, which have been made so far of the nuclear properties of the "new" pile, of the stability of the new fuel elements, and of the safety and practicability of operation of the "new" pile" (p. 2). This report includes table… more
Date: May 24, 1956
Creator: Corngold, N.; Kaplan, I.; Chernick, J.; Gurinsky, D. H. & Fowell, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Testing of Fuel Element Parts and Assemblies by the Radiographic Method

Description: Concurrently with the production of canned uranium slugs for pile operation there arises the problem of nondestructive testing so that no slug which may fail structurally during operation be placed in the pile. The ultimate goal of any such testing program is to devise nondestructive testing methods which will eliminate defective slugs. A secondary goal of the testing program is to learn as much as possible about the construction of the canned slug so that the mechanisms of failure can be under… more
Date: July 1, 1954
Creator: VanderLaan, Robert H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter

Description: Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Date: March 1961
Creator: Yaggee, F. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Observations during the first K West fuel shipping campaign

Description: Three fuel elements were shipped to the 300 Area hotcells during the first characterization shipping campaign from K West Basin. This document summarizes observations made during this campaign including the gas, liquid, and sludge content of the observed canisters. Included in an appendix is a detailed evaluation of fuel element condition for each canister opened
Date: November 1, 1995
Creator: Makenas, B. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Slug Temperatures in an Off-Center Annulus

Description: Abstract. Temperatures are measured at two points in an internally heated jacketed slug which is cooled by water flowing in an off-center annulus around the slug. The variations of these temperatures with water velocity, water temperature, power, and the amount the annulus is off center are measured. The temperature near the slug surface which approaches and comes in contact with the water jacket does not increase as much as anticipated. The temperature near the slug surface on the side which i… more
Date: October 10, 1944
Creator: Kratz, H. R.; Peterson, R. & Schlegel, Richard, 1913-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Slug Jacket Temperatures

Description: Abstract. A method for calculating jacket temperatures in a region of varying heat transfer coefficients is given Some applications are made for temperatures above a supporting rib.
Date: November 8, 1944
Creator: Schlegel, Richard, 1913-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Roll Cladding Uranium-Zirconium and Uranium-Zirconium-Niobium Alloys with Zircaloy-2 for Plate-Type Fuel Elements

Description: From Abstract: "Investigations were made of alternate methods of bonding fuel shapes and the use of alternate core alloys in flat plates. Alternations and additions were made to development facilities needed to fabricate roll-clad plates for the EBWR core. Pilot production of EWBR-type plates proved that the plate cladding process could be adapted to production facilities."
Date: February 1958
Creator: Bean, C. H.; Macherey, R. E. & Lindgren, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Rates of Reaction of Irradiated UO2 and Uranium Metal with Sulfuric Acid

Description: In the decladding of stainless steel clad fuel elements with sulfuric acid (the Sulfex process), the loss of core material to the decladding solution is determined by the rate of reaction of the core material with the solution and the time of exposure if the core to the solution. Since very little was known about the effects of irradiation history on the rates at which core materials dissolve in sulfuric acid, the present study was undertaken in an effort to determine the magnitude of such effe… more
Date: August 13, 1959
Creator: Swanson, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Welding Process for Spire-Can Fuel Elements

Description: The components for the present aluminum clad, Al-Si bonded, internally and externally cooled (I & E), uranium fuel elements are composed of impact extruded cans and spire caps as shown in Figure 1. This type of component requires two impact extrusions; however, in December, 1957, J. E. Ruffin proposed another design of component in which there was only one impact extrusion. For this component, Figure 2, the spire was impact extruded as a part of the can.
Date: March 11, 1960
Creator: Hanson, G. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Ceramic Investigations of UO₂

Description: This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date: June 16, 1955
Creator: Allison, Adrian G. & Duckworth, Winston H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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