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Depassivation of 304-L Stainless Steel in Sulfex Decladding Solutions

Description: In the Sulfex process, stainless steel cladding, generally 304-L, is removed from fuel elements by dissolution in boiling four to six molar sulfuric acid. When cladding removal is complete, the decladding solution is removed is removed to waste. The exposed fuel cores are rinsed and dissolved in nitric acid.
Date: June 30, 1960
Creator: Duke, E. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Twin Argon Welding of Alsi-Bonded Aluminum Clad Uranium Metal Fuel Elements

Description: In the continuing search for better methods of effecting the secondary fusion welded closure in Alsi bonded aluminum clad uranium metal fuel element, an article on "The Twin-Argon Welding Process" by J. A. Donellon was recently found in the September 1954 issue if the British Welding Journal. From a review of the article, the process appeared to have enough possibilities to warrant exploring it. Communication were established with the General Electric Company, Ltd..
Date: May 6, 1960
Creator: Correy, Thomas B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EGCR Lattice Radial and Angular Power Distribution 2.6 w/o Enrichment

Description: The measurements reported here are companion measurements to those reported earlier in HW-63585. The only significant difference between the measurements is that 1.8 w/o enrichment UO2 fuel was used for the first set, and 2.6 w/o enrichment UO2 fuel was used for the measurements described in this report. The new results will be presented graphically, and for completeness, the details of the measurement will be included here as well as in HW-63585.
Date: May 10, 1960
Creator: Nichols, P. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aluminum Alloy Work at Hanford

Description: Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.
Date: May 6, 1960
Creator: Bowen, H. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unclassified Research and Development Programs Executed for the Division of Reactor Development and the Division of Research April 1960

Description: A 19-rod Zircaloy-clad half-length PRTR spike element successfully irradiated to high plutonium burnout at full power in the ETR shoved partial bonding of the core and cladding. Unsatisfactory autoclave films on the Zircaloy cladding of the PRTR Al-Pu fuel elements are delaying final assembly of the first 30 clusters. Further conditioning of the autoclaves and the availability of permanent etching facilities are expected to correct the present difficulties.
Date: May 10, 1960
Creator: Hanford Laboratories Operation Irradiation Procesing Department
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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L/R Indicator

Description: The evaluation of the inductance of an electrical component is often important in understanding and operating an electrical circuit. Inductance is defined by several equations, the most common being e= -L d1/dt . This equation defines inductance as the constant which relates the back emf produced in an element to the time-rate-of-change of current.
Date: May 20, 1960
Creator: Minor, G. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Hydraulic Bases for Selected PRTR Process Specifications

Description: This document presents the bases for those PRTR Process Specifications involving considerations of heat transfer and fluid flow. It will be noted that some of the bases incorporate information gained from laboratory experiments with electrically heated test sections simulating PRTR fuel elements. These experiments are described in some detail elsewhere.
Date: April 1, 1960
Creator: Batch, J. M. & Ambrose, T. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Study of the Wear and Galling of Autoclaved Zircaloy-2 By Various Materials

Description: This is the third of a series of reports describing the phases of a study of the wear and galling of autoclavedZircaloy-2 by various bearing surface materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 surfaces will not prevent scratching. It also showed that metals softer than Zircaloy-2 in general do not scratch it. The second report (2) described how eight metals and alloys were wear-tested on autoclaved Zircaloy-2 as prospects for fuel elemen… more
Date: July 5, 1960
Creator: Weber, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Invention Report: Hermetically Sealed Closure on a Sheathed Thermocouple

Description: Applications of sheathed (metal) thermocouples may require in many instances, the insertion of the thermocouple thermal junction into an area that must be hermetically sealed to the outside. This same area usually contains highly reactive heat transfer medium such as an eutectic alloy of sodium and potassium of sodium alone. When fissionable materials are being irradiated, fission products that are driven off would also be present and must be contained under varying temperatures and pressures.
Date: July 12, 1960
Creator: Kosut, Bert S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Non-destructive Testing Hanford Fuel

Description: At present, emphasis is being given the application of nondestructive testing to the inspection of nuclear fuel in conjunction with complete product specifications. The objective is to quantitatively specify fuel quality parameters, and to measure the entire fuel production against these specifications nondestructively. Under this concept the acceptability of a given fuel element becomes a well-defined factor readily determined by appropriate nondestructive tests.
Date: June 22, 1960
Creator: Worlton, D.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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