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Boiling Depressurization Transients
Abstract: An analytical and experimental effort toward a better understanding of the mechanisms involved in nuclear power reactor loss-of-pressure accidents is presented.
Date:
August 1, 1964
Creator:
Halfen, F. J. & Berganzoli, F.
Object Type:
Report
System:
The UNT Digital Library
Multi-Channel Boiling Stability for Sodium Graphite Reactors
Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors.
Date:
March 1, 1962
Creator:
Cappel, H. H.
Object Type:
Report
System:
The UNT Digital Library
Thermal Stress Testing of Beryllium Oxide Moderator Shapes
Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.
Date:
August 1, 1962
Creator:
Sujata, H. L.; King, M. & Waters, F. J.
Object Type:
Report
System:
The UNT Digital Library
Uranium Carbide Transient Heating Experiments - Phase 1
Abstract: Two in-pile capsules containing mock-up uranium carbide fuel rods were subjected to a total of five neutron bursts in the TREAT facility with initial reactor periods ranging from 0.26 to 0.10 sec.
Date:
August 1, 1964
Creator:
Stachura, S. J.; Silberberg, M. & Cordy, R. N.
Object Type:
Report
System:
The UNT Digital Library
The Chemical Effects of 1 Mev Electrons on BrF3 at 25 degrees C
"An investigation of the chemical effects of 1-Mev electrons on BrF3 at 25 degrees C has been carried out. Pressure measurements taken during the irradiation suggest the presence of Br2 and BrF5 as decomposition products and a fractional distillation of the irradiated liquid confirmed their presence. The extent of decomposition was determined both by fraction distillation and spectrophotometric methods. The radiation effect seemed to reach saturation when approximately 10 per cent of the BrF3 was destroyed. The exposure necessary for the decomposition products to reach a concentration of half the saturated value was calculated to be 2.7 microampere hours/cc BrF3 while the "G" value was found to be 1.5. A qualitative comparison of irradiation dosages from the Statiltron with that expected from spent fuels revealed that little decomposition of BrF3 reagent is to be expected from 1-say cooled Hanford fuel (in pile for 100 days) while in the case of 1-day cooled MTR type fuel (in pile for 12 days) a saturated effect might be realized in 1-3 hours. Since at most only 10 per cent of the BrF3 is destroyed it is concluded that BrF3, from a radiation resistance standpoint, is a suitable standpoint, is a suitable reagent for …
Date:
October 1, 1954
Creator:
Yosim, S. J.
Object Type:
Report
System:
The UNT Digital Library
Sodium Graphite Reactor, Quarterly Progress Report, March-June 1954
"The Atomic energy Commission has undertaken a development program to provide the technology needed for the evaluation and economic design of nuclear power plants. This program is to be carried out during the next five years at several national laboratories and industrial organizations. The Sodium Graphite Reactor (the SGR) is one of those to be investigated and experimentally tested as part of this 5-year effort. The program on the SGR is intended to expand our area of information covering sodium-graphite technology, experimentally demonstrate the feasibility of this reactor complex and extend its performance limits, and apply in information developed to designs suitable for the full-scale nuclear power plant. As a principal part of this program, a Sodium Reactor Experiment (the SRE) is to be constructed and operated; it will be the major experimental facility in which the performance of this reactor will be studied and new technological advances tested. This report continues an earlier series 2-7 in which previous work on the SGR and the SRE has been described. In this report, the progress on the program is described in two main sections. Section A is devoted to work relating to the general technology of Sodium Graphite Reactors, and to …
Date:
September 1, 1954
Creator:
Siegel, Sidney & Inman, Guy M.
Object Type:
Report
System:
The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Period Ending January 15, 1945
Technical report with short reports covering (1) Effect of radiation on water and aqueous systems; (2) Effect of neutrons on graphite; (3) Effect of radiation on solid compounds; and (4) Scattering, stopping-power, ion-pair production, etc.
Date:
February 1, 1945
Creator:
Burton, Milton, 1902- & Allen, A. O. (Augustine O.)
Object Type:
Report
System:
The UNT Digital Library
Preliminary Report on a Colorimetric Method for the Determination of Microgram Quantities of Thorium : Experiments in the Dissolution of O2 Metal [UO2]
Abstract. thorium can be precipitated as a salt of p-dimethylaminoazophenylarsonic acid at a pH of about 1.5. the precipitate, collected on a sintered glass filter is washed with dilute ammonium hydroxide to dissolve the dye. the amount of thorium is determined by measuring the concentration of the dye spectrophotometrically at a wavelength of 450 millimicrons. Zirconium, which interferes, can be separated and determined using the same reagent in strong hydrochloric. the behavior of thorium metal upon treatment with various acids and upon fusion withKHSO4 is described. three satisfactory procedures are given for dissolving the metal with sulfuric acid, phosphoric acid, and by a potassium hydrogen sulfate fusion. The laboratory was presented with the problem of analyzing for a large number of elements in O2 metal. the results of a systematic study of methods for effecting solution of the metal are offered here since they may be of some interest and use to other laboratories. The four methods which effected complete solution of the metal are (1) Sulfuric acid method; (2) Fusion method; (3) Phosphoric acid method; and (4) Nitric acid-hydrofluoric acid method.
Date:
January 1, 1945
Creator:
Byerly, W.; Niedrach, L.; Davin, W.; Dyas, H. & Bane, R. W.
Object Type:
Report
System:
The UNT Digital Library
Thermal Conductivity of Silicon and Iron From 300 to 1400°K
From Abstract : "The thermal diffusivities of pure silicon and of Armco iron have been measures from 300 to 1400°K. The specific heats of the same materials have been measured over the same temperature range."
Date:
January 1, 1963
Creator:
Klein, A. H.; Shanks, H. R. & Danielson, G. C.
Object Type:
Report
System:
The UNT Digital Library
A Study of Thorium Peroxide Sulfate
Abstract. Thorium peroxide was precipitated from thorium nitrate solutions containing varying amounts of sulfate ion and of hydrogen ion. The washed solids were analyzed both wet and dry. Analyses were made for thorium, peroxide oxygen, sulfate, nitrate, and water contents. X-ray powder photographs of the dried samples by W.H. Zachariasen showed the presence of only two phases. When precipitated from high sulfuric acid, the solid phase was isomorphous with Th(OO)SO4.3H20. More weakly acid solutions whose sulfate content was varied over wide limits [SO4--/Th(IV) (in solution before precipitation) = 0.005 to 67.0] yielded a solid, isomorphous with thorium peroxide nitrate and containing 3.0 to 3.8 peroxide oxygen atoms for each thorium atom. The sulfate content of this latter phase varied continuously between the limits SO4--/Th(IV) = 0.34 to 0.01 with nitrate ion present when the sulfate content was very low. This continuous variation in composition is in agreement with the previously proposed structure of this phase.
Date:
October 1, 1945
Creator:
Hamaker, John W.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Report August 1947 to November 1947, Biology Division
The following document is a compilation of quarterly reports from August 1946 to November of 1947 from the Biology Division of the University of Chicago.
Date:
November 1, 1947
Creator:
Brues, Austin M.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Report May 1947 to August 1947 : Biology Division
The following documents were compiled into a quarterly report that was to be published in the Radiobiology Volume of the PPR. The following reports provide data from the Biology department of the University of Chicago between May and August of 1947.
Date:
August 1, 1947
Creator:
Brues, Austin M.
Object Type:
Report
System:
The UNT Digital Library
Testing of Counter-Scaler Units for Statistics
Report discussing the results of an investigation of a test for statistical consistency of counter-scaler units.
Date:
January 1, 1945
Creator:
Coveyou, R. R.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Merchant Ship Reactor Shield Design Summary Report
Abstract: "Most of the Nuclear Merchant Ship Reactor (NMSR) shield design work performed by The Babcock & Wilcox Company (B&W) is summarized. Primary and secondary shield results are presented, consistent with contractual requirements and designated design criteria. Methods of calculation and basic parameters are shown" (p. 1).
Date:
August 1, 1959
Creator:
Smith, W. R. & Turner, M. A.
Object Type:
Report
System:
The UNT Digital Library
Enrico Fermi Fast Breeder Reactor Plant
This report contains a description of the reactor plant portion of the Enrico Fermi Atomic Power Plant, with emphasis on the reactor system. Since this plant contains a developmental reactor, emphasis has been placed on reactor safety and on achieving reliable operation. The design is conservative and is flexible enough to permit incorporation of the results of developmental programs, which include nonnuclear, full-scale component test facility operations, and nuclear experiments, such as critical experiments.
Date:
November 1, 1956
Creator:
U.S. Atomic Energy Commission
Object Type:
Report
System:
The UNT Digital Library
A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator
Abstract: "The Oak Ridge National Laboratory proposes to build an isochronous eight-sector proton cyclotron to provide an extracted beam in excess of 100 A at 810 MeV. The primary proton beam and the secondary meson and neutron beams will be used to investigate nuclear structure, and the interactions between elementary particles. Biomedical and Space-oriented research programs are also planned. Shielded research areas and an extensive beam transport and analysis system are provided. Theoretical and experimental studies have shown that the Mc2 Cyclotron is a practical concept; high extraction efficiencies can be obtained, and the residual radiation problems are manageable. The project would require less than seven years to complete, and would cost about $43,000,000."
Date:
November 1, 1963
Creator:
Oak Ridge National Laboratory
Object Type:
Report
System:
The UNT Digital Library
Liquid Metal Loops Irradiated on the ORNL Graphite Reactor and the LITR
From abstract: Liquid alkali metals were circulated in a series of structural alloy loops under reactor radiation at high temperature. The first of these loops was a lithium-stainless steel (type 316) system, and the remainder were sodium-Inconel. No effect of radiation other than radioactivation was found. Mass transfer and metallurgical processes attributable to the operating temperatures were observed."
Date:
June 1, 1959
Creator:
Parkinson, W. W. & Sisman, O.
Object Type:
Report
System:
The UNT Digital Library
A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor
From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.
Date:
February 1, 1954
Creator:
Henrie, J. O. & Weisner, E. F.
Object Type:
Report
System:
The UNT Digital Library
High Temperature Liquid Metal Circulating System
Introduction: The purpose of this experiment was to demonstrate that a liquid metal heat transfer system could be built and operated at very high temperatures.
Date:
August 1, 1954
Creator:
Keen, R. D.
Object Type:
Report
System:
The UNT Digital Library
Sodium Reactor Experiment Pump Development
Design and operational techniques are described for a freeze seal type centifugal pump for use in the Sodium Reactor Experiment.
Date:
January 1, 1957
Creator:
Cygan, R.
Object Type:
Report
System:
The UNT Digital Library
Radiometric Analysis of Thick Samples
Introduction: Measurements of polonium content in solids are usually performed by dissolving the material and preparing a thin sample which can be measured with one of the available instruments. A measurement of the radiation emerging from the thick sample should be sufficient to evaluate the polonium content. For this reason a calculation has been performed and the results have been compared with those obtained by the thin sample method. Obviously this proposed method using thick samples would be faster.
Date:
March 1, 1944
Creator:
DeBenedetti, Sergio
Object Type:
Report
System:
The UNT Digital Library
The Detection of Small Amounts of Fluorine in Large Amounts of Chlorine
Abstract: "Tests have been developed for both the qualitative detection and quantitative determination of fluorine in chlorine. The qualitative test is made by passing the gas through manganous chloride. If the pink solid tubes brown there is greater than 0.5 percent of fluorine in the gas. The quantitative test is a modification of the Steiger and Marvin Test with oxidized titanium solution."
Date:
April 1, 1946
Creator:
Lafferty, Robert H., Jr. & Winget, Rasho
Object Type:
Report
System:
The UNT Digital Library
Topical Report on Literature Survey of Treatments for Monazite Sands
The following report covers the literature available in the Battelle library as well as the Atomic Energy Commission (New York, N.Y.) on the processing of monazite sands for thorium and rare earth contents.
Date:
November 1, 1947
Creator:
Willigman, M. & Slowter, E. E.
Object Type:
Report
System:
The UNT Digital Library
Mound Laboratory Liquid Waste Disposal Research Quarterly Report for January - March, 1950
The following report follows a complete radiochemical analysis that has been made on the sample of first-cycle neutralized waste, as well as a gravimetric analysis made on the sludge in the sample of first-cycle waste.
Date:
April 1, 1950
Creator:
Monsanto Chemical Company
Object Type:
Report
System:
The UNT Digital Library