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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
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Clad thickness variation N-Reactor fuel elements

Description: The current specifications for the cladding on {open_quotes}N{close_quotes} fuels were established early in the course of process development and were predicted on several basic considerations. Among these were: (a) a desire to provide an adequate safety factor in cladding thickness to insure against corrosion penetration and rupture from uranium swelling stresses; (b) an apprehension that the striations in the zircaloy cladding of the U/zircaloy interface and on the exterior surface might serv… more
Date: May 12, 1966
Creator: Smith, E. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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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ALARA notes, Number 8

Description: This document contains information dealing with the lessons learned from the experience of nuclear plants. In this issue the authors tried to avoid the `tyranny` of numbers and concentrated on the main lessons learned. Topics include: filtration devices for air pollution abatement, crack repair and inspection, and remote handling equipment.
Date: October 1, 1993
Creator: Khan, T. A.; Baum, J. W. & Beckman, M. C.
Item Type: Refine your search to only Report
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
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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
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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
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Examination of enriched ruptured element from 2955C (RM 452)

Description: A CIIIE (enriched) element, one of two elements which failed April 5, 1962 in tube 2955C, was shipped to the Radiometallurgy Laboratory for detailed examination. The element was 21st from the downsteam end. A more severe rupture which occurred in the 19th piece from the downsteam end was believed to have caused the initial rupture indication. After a hot startup a heat cycle developed in the part of the reactor containing tube 2955 increasing the bulk water temperature about 20 per cent. At abo… more
Date: August 21, 1962
Creator: Gruber, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Status of Harvey aluminum component evaluation: Production test IP-12-A

Description: About 298,000 OIIIN aluminum components were received from Harvey for evaluation after major steps were take in the vendor`s plant to upgrade product quality. This material met HAPO specifications and was comparable to Alcoa control components. Finished fuel elements (non-bumper and bumper) canned in the test and control components are tabulated by uranium core type and canning month. Non-destructive and destructive test data did not show any differences in clad fuel elements attributable to co… more
Date: February 13, 1963
Creator: Blanton, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comment issue - Production Test IP-333-D: Irradiation of one defected UO{sub 2} fuel element assembly

Description: To permit the irradiation of one dummy fuel element assembly for one operating period and to permit, during a subsequent operating period, the irradiation of one defected, four-rod-cluster UO{sub 2} fuel element assembly, in a KE front-to-rear test hole. The fuel material is natural UO{sub 2} of 95 per cent theoretical density; the cladding is zircaloy. The defect in the assembly is artificial and will be made before irradiation by drilling a .005in. diameter hole through the cladding near the … more
Date: June 14, 1960
Creator: Marshall, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
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Program for Crud and Corrosion Studies for Proposed Hanford Reactor Conditions

Description: This report presents a proposed test program to study the corrosion of aluminum-clad fuel elements under conditions expected at the more severe conditions which will be encountered in operating the present Hanford reactor at higher power levels.
Date: September 6, 1960
Creator: Richman, R. B. & Dickinson, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Testing of Zircaloy-2-Clad Uranium Seven-Rod Fuel Elements. Final Report

Description: In 1955 the Fuels Development Operation began irradiation testing of fuel elements in high temperature water. It was assumed that if a new reactor were built at Hanford, it would be cooled by high-temperature, pressurized water. Corrosion tests showed that aluminum-clad production fuel elements could not be used in high-temperature water. Therefore, while work to improve the resistance of aluminum to high-temperature water proceeded, the Fuel Design Operation began irradiation of stainless stee… more
Date: July 5, 1960
Creator: Geering, G. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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C reactor overbore fuel failures

Description: The concept of overboring the graphite channels in an older Hanford reactor and installing oversized tubes charged with oversize fuel elements is being investigated at C reactor. Recently a column of these oversized test fuel elements exhibited three uranium cleavage (split) type failures after experiencing severe reactor flux cycling. This report presents a preliminary description of both the fuel failures and the flux cycling encountered by the reactor.
Date: April 30, 1962
Creator: Ambrose, T. W. & Graves, S. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PT IP-416 measurement of the horizontal rod strength at H Reactor. Final report

Description: The object of this test was to obtain data concerning the reactivity of the horizontal rods in the E-N fuel loading at H Reactor. An accurate calibration of the control rods could then be used to provide a more accurate measurement of the other reactivity variables associated with the E-N loading. A comprehensive rod calibration test was performed at H Pile in 1957. Results of the present test, needed because of the ``blacker`` E-N fuel in the pile, have been normalized to the 1957 test results… more
Date: January 24, 1962
Creator: Vaughn, A. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-603-I evaluation of accidental fuel flushing potential D-DR reactors

Description: This purpose of this test is to acquire data to support further studies aimed at determining whether a normal column of I&E enriched fuel elements or a normal column of natural fuel elements can be flushed from a process tube with the crossheader valved down to shutdown position if the front riser pressure is raised to normal operation pressure.
Date: July 30, 1963
Creator: Hollifield, P. J. & George, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fabrication of hot die size diffusion bonded fuel elements for Production Test IP-546-A

Description: Hot die sizing (HDS) is a process being considered at Hanford to replace or supplement the existing AlSi brazing process. Hot die sizing consists of passing a preheated core-component fuel assembly through a cold the to bond the aluminum jacket to the core while passing a die plug through the internal bore to form the internal bond. Fuel end bonding is accomplished in a following step by applying heat and pressure to the sized fuel element. This report summarizes the fabrication of fuel element… more
Date: October 10, 1963
Creator: Strand, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Outer annulus imbalance study: Mark I fuel

Description: Results of an investigation of fuel element outer annulus enthalpy imbalance are reported and analytical results of suggested methods to limit this imbalance are presented. Also included are comparisons of calculated and experimental enthalpy imbalance ratios along with other quantities. Results indicate that tightening fuel tolerances and clearances can substantially reduce the present outer annulus imbalance thereby increasing power capability. A basic pre-requisite to reduction of clearance … more
Date: April 26, 1966
Creator: Long, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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