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In-reactor corrosion of X-8001 and 1245 aluminum: Analysis of data from PT IP-42A

Description: Failures of standard fuel element jackets (1245 aluminum alloy) after relatively short Hanford reactor exposures are occurring at high reactor power levels. Metallographic examination of fuel element jackets from short exposure ruptures shows the cause of failure to be rapid intergranular corrosion. This type of attack has been reproduced in laboratory tests by exposure to water at temperatures above 200 C, or to steam at temperatures higher than 300 C. Flow disruptions due to misalignment of t… more
Date: June 25, 1958
Creator: Dillon, R. L. & Richman, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hydrofluosilicic acid as a cap and can etchant

Description: Aluminum caps and cans are thoroughly cleaned, before being used to can slugs, to insure wetting of the metal surfaces by molten AlSi in the canning pot. An acid bath is used, as part of the cleaning operations to remove surface oxide and other surface films from the metal. Two acid solutions are authorized in the standard operating procedure; a 20% phosphoric acid solution for etching both caps and cans, and a 1% hydrofluosilicic acid solution to be used for caps only. It is desired to determi… more
Date: March 17, 1953
Creator: Dixon, D. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proceedings of the 1988 International Meeting on Reduced Enrichment for Research and Test Reactors

Description: The international effort to develop and implement new research reactor fuels utilizing low-enriched uranium, instead of highly- enriched uranium, continues to make solid progress. This effort is the cornerstone of a widely shared policy aimed at reducing, and possibly eliminating, international traffic in highly-enriched uranium and the nuclear weapon proliferation concerns associated with this traffic. To foster direct communication and exchange of ideas among the specialists in this area, the… more
Date: July 1, 1993
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Evaluation of etchants for deoxidizing aluminum components

Description: In the canning operation, the preparation of aluminum components is important in assuring uniform wetting of the aluminum surfaces with Al-Si. The surfaces of the components should be free of dirt and grease and should also have a minimum retention of non-metallic film, normally aluminum oxide, for the best wetting properties. At present, dirt and grease are removed satisfactorily by a vapor degreaser followed by a Duponol-alkaline wash. The standard specified method of removing the aluminum ox… more
Date: April 15, 1953
Creator: Weakly, E. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HAPO irradiation of capsules containing UO{sub 2} specimens

Description: A knowledge of the effect of reactor irradiation on the properties of UO{sub 2} is relevant to the design and evaluation of UO{sub 2} fuel elements for the PRTR. Of particular interest is the effect of reactor irradiation on the thermal conductivity of sintered UO{sub 2} and the type, mechanism, and extent of radiation damage in sintered UO{sub 2}. In the latter case the study of fractured surfaces of irradiated UO{sub 2} specimens is a method of determining the extent of radiation damage. It i… more
Date: February 17, 1958
Creator: Newkirk, H. W.; Millhollen, M. K. & Brite, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Electrorefining {open_quotes}N{close_quotes} reactor fuel

Description: Principles of purifying of uranium metal by electrorefining are reviewed. Metal reactor fuel after irradiation is a form of impure uranium. Dissolution and deposition electrorefining processes were developed for spent metal fuel under the Integral Fast Reactor Program. Application of these processes to the conditioning of spent N-reactor fuel slugs is examined.
Date: February 1, 1995
Creator: Gay, E. C. & Miller, W. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fission product release rate from aluminum clad uranium fuel

Description: The rate of fission product inventory release to the environment as a result of exposure of uranium fuel to high temperatures should be known to more realistically assess the consequences of a credible accident. To obtain an acceptable experimental evaluation of releases it is necessary to have similar conditions to those which would exist in the reactor. Fission product release rate experiments exploring temperatures below the uranium melting point were performed for Douglas United Nuclear by … more
Date: March 22, 1968
Creator: Traxler, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Supplement F, Production Test IP-314-A, Measurement of fuel element temperature changes as the result of film deposition

Description: This document discusses the test program of evaluating the temperature effect of crud film build-up on fuel element heat generating surfaces in a carbon steel system. This program has three phases: Measurement of the effect of film build-up during normal high pH equilibrium operation; measurement of the temperature effect of film build-up subsequent to a loop decontamination; and measurement of the effect of film build-up in the event of loss of pH control.
Date: November 21, 1960
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design and fabrication of target elements for PT-645-D

Description: Target elements were designed and built to fit into 1.25% U{sup 235} driver elements. These targets had an aluminum -- 0.583% lithium alloy core enriched to 63.5% in Li. The targets had a coextruded aluminum jacket as a tritium barrier and a Zircaloy jacket as a corrosion barrier to the 300 C reactor water.
Date: March 9, 1964
Creator: Tverberg, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Using low-enriched uranium in research reactors: The RERTR program

Description: The goal of the RERTR program is to minimize and eventually eliminate use of highway enriched uranium (HEU) in research and test reactors. The program has been very successful, and has developed low-enriched uranium (LEU) fuel materials and designs which can be used effectively in approximately 90 percent of the research and test reactors which used HEU when the program began. This progress would not have been possible without active international cooperation among fuel developers, commercial v… more
Date: May 1, 1994
Creator: Travelli, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

University Loaned Normal Uranium Slug Disposition Study: University survey responses. Predecisional draft

Description: During the 1950`s and 1960`s, the Atomic Energy Commission loaned rejected natural uranium slugs from the Savannah River Site to United States universities for use in subcritical assemblies. Currently, there are sixty-two universities holding 91,798 slugs, containing about 167 metric tons of natural uranium. It was originally planned that the universities would return the material to Fernald when they no longer required it. Fernald has not received slugs since it was shut down in 1988. The Depa… more
Date: September 1, 1992
Creator: Becker, G. W. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Recovery of weapon plutonium as feed material for reactor fuel

Description: This report presents preliminary considerations for recovering and converting weapon plutonium from various US weapon forms into feed material for fabrication of reactor fuel elements. An ongoing DOE study addresses the disposition of excess weapon plutonium through its use as fuel for nuclear power reactors and subsequent disposal as spent fuel. The spent fuel would have characteristics similar to those of commercial power spent fuel and could be similarly disposed of in a geologic repository.
Date: March 16, 1994
Creator: Armantrout, G. A.; Bronson, M. A. & Choi, Jor-Shan
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

KER-3 operating report test K-3-13, PT-1P-363-A. Irradiation of ZR-2 jacketed enriched single tube fuel elements in the KER Loops

Description: The objective of the test was to evaluate the behavior during irradiation of nominally 1.739 inch OD, 1.074 inch ID, Zircaloy-2 jacketed single tube fuel elements with brazed end closures at operating conditions somewhat more severe than those expected for N Reactor fuel element outer tubes. The test elements were fabricated with the Be-Zr alloy brazed end closure planned for use on N Reactor fuel elements. Iron supports were used to minimize process tube scratching during charge-discharge.
Date: June 12, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production Test IP-168-A, Long term corrosion monitoring and evaluation of operating limits for I & E charges -- C-Reactor

Description: The performance of I & E fuel elements under the original tests{sup 1} was such that they are now being charged at C Reactor on a production basis. Data obtained from the original test, however, were not sufficient to indicate long term corrosion effects of the use of these elements, nor to accurately define their operating characteristics. It is the intent of this test, therefore, to provide for long term corrosion monitoring in tubes charged with and without water-mixing pieces; and to obtain… more
Date: June 11, 1958
Creator: Hall, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production reactor process tube, dummy, and fuel element cladding film and radioactivity studies

Description: During the normal operation of reactors ionic, particulate and colloidal substances in the coolant are activated as they pass through the neutron flux. The parent substances for the activated materials come from several sources: transient corrosion products from the coolant system piping and fuel element cladding, coolant additives and coolant impurities. Previous studies have shown that a major portion of these substances do not simply pass through the neutron flux field but undergo complex so… more
Date: March 14, 1962
Creator: Perrigo, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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