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Fluidized-Bed Calcination Studies with Stimulated ICPP Waste Solution

Description: At the present time, high-radioactivity-level wastes at Hanford are neutralized and stored as liquid in underground tanks lined with mild steel. This method of storage is relatively inexpensive and is satisfactory on a short-term basis. However, on a long term basis, liquid storage is less desirable than solid storage because of the greater mobility of the liquid. In addition, storage as aa solid would significantly reduce the volume of waste stored. Consequently, various research and developme… more
Date: June 6, 1960
Creator: Schneider, K. J.
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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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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Classification of PuO2 Particles

Description: The Biology Operation, Hanford Laboratories, required plutonium dioxide particles in five different micron and sub-micron size ranges. These were to be supplied as a water suspension in small containers. It was necessary to design equipment, suitable for hood operation, which would give a satisfactory separation of these particles.
Date: January 6, 1960
Creator: Burnham, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Specification for Requisition G-3855923Xircalogy-4 Jacket Tubing

Description: This specification is specifically designed for the procurement of Zircaloy tubing to be used in the of swaged, UO fuel elements, an, and the Pu fuel elements for the Plutonium Recycle Test Reactor. Requisition G-385923 contains the following information pertinent to this specification: 1. Dimensions and dimensional tolerance. 2. Source of zirconium sponge and conditions for us of Zircaloy scrap. 3. Inspection requirements. 4. Shipping instructions.
Date: November 6, 1959
Creator: Oakes, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Confinement System Instrumentation

Description: Instrumentation shall be provided as shown on the attached drawing, SK-1-26835 for Confinement System Control. The Primary objective of the confinement system shall be to provide maximum possible confinement of contamination, consistent with building limitations, in the event of any contamination, consistent with building limitations, in the event of any credible reactor accident resulting from equipment failure or reactor mis operation.
Date: November 6, 1959
Creator: Richards, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Notes on Lattice Parameter Calculations

Description: In the last two or three years there has been a notable improvement in the knowledge and understanding of reactor lattice physics. During this interval, measurements of parameters have been improved and the methods of analysis have been greatly strengthened. It has become apparent that the classical ways for computing the lattice parameters are not sufficient. It is the purpose of this report to publish under one cover as much of the most recent information as possible.
Date: October 6, 1960
Creator: Joanou, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Flow Decay After an Electrical Power Outage in the PRTR

Description: Previously, W. S. Figg and T. W. Ambrose (HW-51767 Rev) have investigated the problem of flow decay following electrical power loss to the PRTR primary coolant pumps. However, since the time of their study many reactor piping changes have been made in the design; therefore, it has become advisable to re-examine the problem incorporating these changes.
Date: February 6, 1959
Creator: Muraoka, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safe Conditions For Applying Titanium In H.A.P.O Process Equipment

Description: A two and one-half year period of extreme caution where titanium and nitric acid are involved has passed since the occurrence of the last and most serious uncontrolled incident involving titanium and nitric acid. During this period controlled explosions involving titanium and nitric acid have been routinely reproduced, additional laboratory and pilot plant experience has been gained and successful industrial applications have been appraised. Based on laboratory data and the known industrial exp… more
Date: October 6, 1956
Creator: Smith, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion of Aluminum in Tap Water

Description: The introduction of aluminum in hot process water has been studied extensively and numerous reports have been issued on the subject. The conclusions reached have been largely empirical and can only be used to state what is happening under the given conditions existing in the corrosion experiments. It is only with difficulty and a great deal of uncertainty that these empirical results can be used to predict what will occur under a different set of conditions. If the fundamental mechanism of alum… more
Date: June 6, 1956
Creator: Groot, C. & Troutner, V. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Control Instrumentation and Procedures

Description: This paper discusses technical bases, operating standards, and instrumentation systems required to achieve the goal of nuclear safety in operation of high-level reactors. Because of the relatively long neutron lifetime in a thermal reactor and the comparatively modest time rates of reactivity change associated with fission poison and temperature effects, the rod system used for compensating reactivity transients and for maintaining flux distribution control may be operated manually. Manual oper… more
Date: April 6, 1956
Creator: Fullmer, G. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion of Aluminum in Uranium Nitrate Solutions

Description: At the request of F. W. Albaugh of the Engineering Department, the corrosive effect of 1% uranium nitrate hexahydrate solution on aluminum at 100 C has been measured. The corrosion of aluminum in uranium nitrate solution has been shown in laboratory tests to be too severe to permit the use of aluminum for containing hot uranium nitrate solutions. A minimum corrosion penetration rate of 2 mils per day was observed with M-329 aluminum in 1% uranium nitrate hexahydrate in pH 2 aqueous solution at … more
Date: April 6, 1956
Creator: Troutner, V. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bronze Furnace History 313 Building

Description: This study was started in May 1949 to find methods of reducing the number of element failures in the salt bath bronze furnaces. Determining the cause of the failure and methods of eliminating them is followed to completion.
Date: February 6, 1951
Creator: Correy, Thos. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgical Examination of Resistance Thermometer Elements Removed from 105 KW and KE Areas

Description: This examination was conducted primarily to determine the extent of corrosion existing between the silver bearing alloy and the type 416 stainless steel nut of K reactor units subjected to service conditions and also to establish irrevocably that metallurgical defects exist in the brazes.
Date: June 6, 1955
Creator: Hartcorn, L. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Summary of Small Source Theory Applied to Thermal Reactors

Description: A small source model for neutron flux distribution in heterogeneous reactors is proposed. Such a model takes more explicit account of fuel lumping than has been customary in most pile calculations. The small source is applied to the cases of plate and rod fuel elements. The chief results are equations which give the pile buckling in terms of the distance between fuel elements and in terms of fuel element constants. (W.D.M.)
Date: December 6, 1954
Creator: Horning, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stability of Florothene Under Exposure to Gamma Radiation

Description: The stability of fluorothene (polytrifluorochloroethylene, Kel-F) to gamma radiation has been investigated to estimate the probable life expectancy of fluorothene equipment exposed to Purex process solutions. Samples of fluorothene were exposed to total gamma radiation dosages up to 10 degree R. The results of these tests substantiate the findings reported by Sisman and Bopp in their compilation of data on the affects of radiation on plastics.
Date: July 6, 1956
Creator: Adler, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion Effects of Lowering the pH in TBP Waste Storage Tanks

Description: Large savings in waste storage space may be realized by lowering the pH at which TBP waste is stored. Additional savings in neutralizing chemicals and operating time would also increase the monetary gain from such a process change. However, before such a change could be made, the corrosive effect of TBP waste at a lower pH on the mild steel waste storage tanks had to be determined.
Date: April 6, 1954
Creator: Groves, N. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Maximum Temperature in Thin Rectangular Uranium Wafers

Description: Temperature calculations have been made to aid in planning a production test for low level irradiation of the thin rectangular uranium wafers. These uranium wafers, under irradiation in the outer fringe sone, are expected to have a maximum temperature which is less than 10 C above the local water temperature.
Date: January 6, 1954
Creator: McNutt, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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