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N. S. Savannah Fuel Design and Development Program: Fuel Rod Vibration (Preliminary Report)

Description: This is a preliminary report on the investigation of the N.S. Savannah replacement fuel rod vibration amplitude when excited by water flowing parallel to the axis of the fuel rod. Methods of calculating the fuel rod frequency in air were verified by experiment. Work is continuing to establish the validity of methods of calculating natural frequencies in water and to confirm the correlation of flow induced vibration amplitude found in reference (1).
Date: September 25, 1959
Creator: Bailey, J. A. & Shields, C. M.
Partner: UNT Libraries Government Documents Department
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Shielding on a 27,300 SHP Boiling Water Reactor Marine Propulsion System

Description: This report summarizes the radiation and shielding analysis for a 30,000 SHP natural circulation boiling water reactor for ship propulsion. The reactor is proposed for installation in a 60,000 DWT, 18 knot tanker of the T-7 class.
Date: July 25, 1959
Creator: Craig, W. D.
Partner: UNT Libraries Government Documents Department
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The Determination of Fission Product Gamma Doses

Description: In this paper arbitrary limits of the general fission source gamma problem are set. Then, by assuming cooling of at least one day, it is shown that only twelve different fission product gamma sources need ever be considered.
Date: February 25, 1957
Creator: Ruehle, William G.
Partner: UNT Libraries Government Documents Department
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The Chemistry of Vanadium: A Summary of the Non-Project Literature Through November, 1952

Description: The non-project literature concerning the chemistry of vanadium has been summarized through November, 1952. The report is presented in terms of izo- and heteropoly vanadates and cationic forms of pentavalent vanadium, complexes of di-, tri-, and pentavalent vanadium, and oxidation potentials of various vanadium systems. A bibliography of 93 references is included.
Date: June 25, 1954
Creator: Frank, Andrew J.
Partner: UNT Libraries Government Documents Department
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A Combined Distillation-Electrochemical Method for Recovery of Hydrofluoric Acid

Description: Electrodialysis in an ion-exchange membrane cell was shown to be technically feasible for the concentration of an azeotropic mixture of HF and water. A flowsheet is presented for recovery of anhydrous HF by distillation and electrodialysis of the azeotropic residue. In the electrodialysis step, 2.6 kwhr of energy per pound of anhydrous product was consumed, with electricity at 1¢ per kilowatt-hour, the total operating cost of the electrodialysis equipment alone, including amortization, would be… more
Date: May 25, 1956
Creator: Marinsky, J. A. & Giuffrida, A. J.
Partner: UNT Libraries Government Documents Department
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Preliminary Results of APPR Critical Experiments, Part I.

Description: This memorandum is the first in a series reporting progress in the program of critical experiments in the ORNLArmy Package Power Reactor Project. The critical assembly, designated as CA-25, is analogous to the APPR design core and consists of 45 fuel boxes, in a 7 x 7 array with the corners removed, contaIned in a large water tank. Two sides of each box are slotted for the insertion and positioning of any desired loading of eighteen plates of fuel, structural material, and poison. The array is … more
Date: November 25, 1955
Creator: Williams, D. V. P.
Partner: UNT Libraries Government Documents Department
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Pb-Sn Alloy Replacements for UO2 Density Standards

Description: A correlation between the optical densities if the Pb-Sn alloy system and UO2 with respect to Co^60 gamma radiation has been determined. This enables one to fabricate density standards of whatever geometry may be desired for one in the gamma absorptiometer by simply casting a Pb-Sn alloy of the proper composition to correspond to the density required.
Date: April 25, 1960
Creator: Christensen, J. A.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on pH Control by Ion Exchange in High pH Systems

Description: The primary purpose of a cleanup system in a recirculating water loop is to maintain the best possible water quality conditions. This is normally accomplished by continuously purifying all or a portion of the coolant. A secondary objective of the cleanup system is to help maintain the system pH at a constant value. A system that will satisfactorily accomplish both of these objectives is at times difficult to obtain. Generally the pH control characteristics are sacrificed in favor of the more im… more
Date: April 25, 1960
Creator: Demmitt, Thomas F.
Partner: UNT Libraries Government Documents Department
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Oxygen Removal with Hydrazine- Interim Report

Description: During normal operation the NPR will function as a closed system and the coolant will be maintained at a high degree of purity. Periodically, however, the system will have to be opened for fuel element discharge and/or decontamination. During these periods the reactor will be operated on single pass cooling. The use of deionized and deoxygenated water as the single pass coolant is not economically feasible due to the large quantities of coolant that will be required. At present it appears that… more
Date: January 25, 1960
Creator: Demmitt, Thomas F.
Partner: UNT Libraries Government Documents Department
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Decontamination of the KER Rupture Experiment Loop. Test Series B - Tests No. 3. Test Series D-Test No. 1.

Description: The first series of tests in the KER-REP-1 loop proved that a fission product contaminated loop could be decontaminated to a safe level for contact maintenance. Since a good decontamination process was available, there was much that could be improved about this process. Further testing of this process and several variations of other processes have been scheduled. The evaluation of these processes includes specific decontamination factors, process corrosion, and loop activity reduction factors (… more
Date: November 25, 1959
Creator: Weed, R. D.
Partner: UNT Libraries Government Documents Department
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Contraction Losses and High Temperature Pressure Drop Determinations for Tube Bundles

Description: In some engineering applications it has become necessary to operate equipment containing small diameter rods or tubes oriented parallel to flow stream. In the case of several nuclear reactors such as the Plutonium Recycle Test Reactor and the S. S. Savannah Maritime Reactor, bundles of small diameter rods are used as the fuel elements. The situation also has application to heat exchangers. A method for accurately predicting the pressure drop characteristics of various bundle configurations woul… more
Date: January 25, 1960
Creator: Gartin, W. J.
Partner: UNT Libraries Government Documents Department
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Stored Energy in BNL Reactor Graphite

Description: Radiation damage to graphite has several consequences of practical importance. The growth of graphite under radiation (Wigner's disease) in production reactors has always been a serious concern. The thermal conductivity of graphite decreases greatly with time of irradiation and is important in long range studies of reactor temperature problems.
Date: February 25, 1953
Creator: Chernick, J.
Partner: UNT Libraries Government Documents Department
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Neutron Streaming Through Boundaries in a Mock-Up of the SIR Rotating Plug

Description: This report is a summary of the neutron attenuation data which have been obtained at the Brookhaven shielding facility on a mock-up of the fuel-rod-unloading plug used in the KAPL Reactor. Before this program was initiated, a number of small scale tests had been made in the ORNL lid tank on carbon steel mock-ups of components of the rotating plug. The results of the tests indicated considerable neutron streaming through the vertical steel and air members of the plug. However, the lid tank sourc… more
Date: March 25, 1953
Creator: Kouts, Herbert, J. C.; Pratt, William, W.; Schamberger, Robert, D.; Shore, Ferdinand, J.; Sleeper, Harvey, P., Jr. & Susskind, Herbert
Partner: UNT Libraries Government Documents Department
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A Test of the Refraction Seismic Method on the Hanford Project

Description: Information was desired on applicability of seismic methods of geophysical exploration in helping to better define and refine hydrological and geological factors affecting ground disposal of liquid radioactive wastes. To date most of information on the area geology has been obtained from surface mapping and well drilling, although it has long been recognized that geophysical techniques may greatly assist in defining the geology of the region. Although direct measurements are generally preferred… more
Date: September 25, 1959
Creator: Raymond, J. R.
Partner: UNT Libraries Government Documents Department
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Measurement of the Nuclear Materials Content of Non-Production Fuels

Description: In considering the problems associated with the measurement of SSNM content of Non-Production Fuels, two distinct problems are apparent. The first is the technical problem of obtaining highly accurate measurements in a complicated chemical and physical system. The second is the administrative problem of choosing a measurement system which provides a basic of financial settlement acceptable to both the seller (reactor operator) and the buyer (Commission).
Date: May 25, 1959
Creator: Schneider, R. A.
Partner: UNT Libraries Government Documents Department
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Artificial Cooling of the Columbia River By Dam Regulation Part 1

Description: In early July, 1958, it appeared that Columbia River temperature at HAPO would be near 24.5ºC by the end of August. River temperature were averaging 4º to 5º above 1957 figures and were 3º to 4º above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent.
Date: May 25, 1959
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Hastelloy F Dissolver Installation in 321 Building

Description: Hastelloy F is a prime contender as a material of construction for plant dissolvers in the power fuel reprocessing program. Consequently, the fabrication and installation of dissolver was undertaken to delineate any unknown problems associated with the use of Hastelloy F; and, at the same time, to provide a vessel for development studies on the Niflex or the Sulfex processes. The purpose of this report is to describe the actual basis for design as well as to present the problems encountered dur… more
Date: May 25, 1959
Creator: Cooley, C. R.
Partner: UNT Libraries Government Documents Department
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Detailed Procedure for K Reactors Rear ace Decontamination by Chemical Flush or the Rear Crossheaders, Pigtails and Nozzles as Authorized by the Production Test Authorization IP-239-N.

Description: The purpose of this procedure is to present a detailed, chronological presentation of the preliminary decontamination and post decontamination steps necessary to fulfill the requirements of the Production Test Authorization IP-239-N. The procedure attempts to present the required operation in sufficient detail to successfully accomplish the intent of the test. Certain procedures involve operations of a standard nature and have not been elaborated upon to any great extent, as it is expected tha… more
Date: February 25, 1959
Creator: Crossman, W.A.
Partner: UNT Libraries Government Documents Department
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Random Loading of E-Metal Dissolver

Description: Nuclear safety in the dissolution of irradiated 0.95 U235 enriched fuel has been investigated. In particular, critical conditions of fuel of this enrichment in a 52-inch diameter dissolver crib were studied. Since a crib this size is not safe by geometry, dissolution procedures as well as maximum safe batch sizes were analyzed. Uranium-water lattices are normally studied in systems in which rods are uniformly dispersed in the moderator. The results of such a study for 1.34-inch diameter solid … more
Date: February 25, 1959
Creator: Ketzlach, M.
Partner: UNT Libraries Government Documents Department
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Radial Thermal Flux Traverses in Natural Uranium - Graphite Lattices

Description: The spatial distribution of thermal neutrons in a reactor lattices cell is of fundamental importance for many reasons. First of all, this information allows the determination of the relative absorption rates in each component of the cell which in turn enables a determination of the thermal utilization, and the diffusion length of the lattice. In addition, the observed spatial distributions of thermal neutrons in the lattice cell is of major interest in testing various approximations to the solu… more
Date: May 25, 1959
Creator: Nilson, R. & Oakes, T. J.
Partner: UNT Libraries Government Documents Department
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Memorandum

Description: We have recently completed measurement of resonance escape probability in the BNL reactor and in several slightly-enriched uranium light water moderated lattices. In addition, WAPD has made available to us data from other slightly enriched uranium-water lattices, so that about 18 lattices in all have been done.
Date: June 25, 1956
Creator: Sher, R.
Partner: UNT Libraries Government Documents Department
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Effects of Low Levels of X-Rays and Irradiation from C14 and H3 on Cell Population Kinetics in the Root Tip of Tradescantia

Description: Reciprocal labelling in double-labelling experiments with H3- and C14- thymidine showed that when H3- thymidine (1μc/ml for 0.5 hr) was given first in the labelling sequence followed by a 4 hr interval before the C14- thymidine treatment, that passage of cells into and out of DNA synthesis was normal. When C14 was first in the sequence, the rate at which cells entered DNA synthesis was decreased. This was attributed to a radiation effect produced by the β-rays from the C14. The rate at which ce… more
Date: March 25, 1963
Creator: Wimber, Donald E.
Partner: UNT Libraries Government Documents Department
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