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Examination of Uranium-2 w/o Zirconium Experimental Fuel Slugs Irradiated in EBR-I. Final Report-Program 6.1.11

Description: Six groups of U-2 wt% Zr fuel slugs were irradiated in the first core of the EBR-I to burnups of 0.080 to 0.189 at.% at calculated temperatures of 307 to 353 deg C. Two groups of cast specimens were found to be more dimensionally stable than four groups of wrought slugs. Of the wrought slungs, the as quenched group showed less tendency to grow than the three groups which had some annealing after quenching. Specimens at burnups of about 0.189 at.% and at 383 deg C showed the onset of swelling as… more
Date: February 1, 1962
Creator: Murphy, W. F.; Klank, A. C. & Paine, S. H.
Partner: UNT Libraries Government Documents Department
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The Effects of Irradiation on Some Binary Alloys of Thorium-Plutonium and Zirconium-Plutonium

Description: A specimen of cast thorium-5 wt% plutonium and one of thorium-10 wt% plutonium were irradiated to total atom burnups of 1.9 and 2.6%, respectively, at maximum fuel temperatures of approximately 450 deg C. Both alloys displayed excellent dimensional stability with volume increases of 0.8 and 1.2% per atom per cent burnup, respectively. Three cold-rolled specimens of zirconium-5 wt% plutonium and one cold-rolled specimen of zirconium-7 wt% plutonium were also irradiated. The zirconium- plutonium … more
Date: July 1, 1962
Creator: Horak, J. A.; Kittel, J. H. & Rhude, H. V.
Partner: UNT Libraries Government Documents Department
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THE EXPERIMENTAL DESIGN FOR BeO IRAADIATION EXPERIMENTS ORNL 41-8 AND ORNL 41-9

Description: The experimental plan for irradiating BeO pellets in Experiments ORNL 41- 8 and ORNL 41-9 was chosen in accordance with the principles of experimental design. The design is known by statisticians as a 2/sup 5/ factorial experiment confound'' in six replications. Five variables---size, density, grain size, temperature and time--are controlled at two levels to form the basic 2i factorial experiment. The sixth variable, neutron flux, is introduced by confounding on higher-order interactions. An ex… more
Date: July 18, 1962
Creator: Gardiner, D.A.
Partner: UNT Libraries Government Documents Department
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A STUDY OF THE SHIELD OF THE UNIVERSITY OF ILLINOIS TRIGA MARK II RESEARCH REACTOR

Description: Detailed measurements were made of the fast-neutron and gamma dose rates and the thermal-neutron fluxes existing at the surfaces of the biological shield of the University of Illinois TRIGA Mark II Research Reactor. Dose rates and fluxes were found to be extremely low. A comparison was made by means of threshold foil techniques between the fast-neutron flux in a beam hole of the reactor during steady-state operation at 1 kw and during a nominal 250 Mw, 30 msec pulse produced by rapid insertion … more
Date: April 23, 1962
Creator: Blosser, T.V.; Freestone, R.M. Jr. & Miller, J.M.
Partner: UNT Libraries Government Documents Department
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Physics Division Summary Report, February-March 1962

Description: Progress is reported in experimental nuclear physics on calculations concerning the distribution of lifetimes of neutrons in glass scintillation neutron detectors and on the probabilities for single, double, and triple scattering of neutrons in thin plates. Precision measurements of gamma-ray energies and intensities were used to modify and extend the level scheme of Hf/ sup 178/. The presence of three K = 0 rotational bands (besides the ground state) and two K = 2 rotational bands are indicate… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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GENERAL STANDARDS GUIDE FOR EXPERIMENTS IN ORNL RESEARCH REACTORS

Description: The Oak Ridge National Laboratory has three generalpurpose research reactors which accommodate testing loops, target irradiations, and beam-type experiments. Since the experiments must share common or similar facilities and utilities, be designed and fabricated by the same groups, and meet the safe safety criteria, certain standards for these have been developed. These standards deal only with those properties from which safety and economy of time and money can be maximized and do not relate to… more
Date: August 20, 1962
Creator: Cagle, C.D.
Partner: UNT Libraries Government Documents Department
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AN ESTIMATE OF THE EFFECT OF NEUTRON-ENERGY SPECTRUM ON RADIATION DAMAGE OF STEEL

Description: The postulate that the average number of lattice displacements is directly proportional to the available energy is carried one step further; it is assumed that damage to steel (particularly in regard to brittle fracture) is proportional to the number of lattice vacancies that occur. The model, although crude, permits estimation of the relative damage resulting from differences in neutron spectra. The results can be used as a rough method of correcting damage data for the effect of the neutron-e… more
Date: July 27, 1962
Creator: Claiborne, H.C.
Partner: UNT Libraries Government Documents Department
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Progress Report on Neutron Radiography

Description: BS> The potential advantages of neutron radiography as an inspection method are discussed along with a historical review and discussions of neutron sources and detectors. The results of the current investigation of neutron-image detectors are discussed in regard to photographic speed, relative neutron-gamma response, and resolution comparisons. Two neutron-image detecting methods are discussed. In one, the direct-exposure method, both the converter screens and the film are exposed to the neutro… more
Date: February 1, 1962
Creator: Berger, H. & McGonnagle, W.J.
Partner: UNT Libraries Government Documents Department
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IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR

Description: A coextruded 2-inch-diameter tubular fuel element of U-2 wt% Zr alloy clad with Zircaloy-2 was irradiated in the Vallecitos Boiling Water Reactor to 1280 Mwd/t burnup with a maximum core temperature of 433 deg C. The purpose of this irradiation was to determine the dimensional stability of the alloy under conditions approaching those contemplated for D/sub 2/O-cooled power reactors. Successive dimensional measurements revealed a sharp change in swelling rate between 700 and 1280 Mwd/t burnup. T… more
Date: April 1, 1962
Creator: Quigley, H.C.
Partner: UNT Libraries Government Documents Department
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NEUTRON-CHARGED PARTICLE REACTIONS. THE ANALYSIS OF THIN LITHIUM AND BORON FILMS

Description: Thin Li/sup 6/F and B/sub 2/O/sub 3/ films were nondestructively analyzed by bombarding them with neutrons, obtaining the pulseheight distribution of the resultant charged particles, and determinlng the number of reactions from the area under each peak in the spectrum. The results agreed within the precision of this method with results of a flame analysis. This method is more accurate and sensitive than conventional neutron activation methods. (D.C.W.)
Date: January 1, 1962
Creator: Finston, H.L.; Wellwart, Y. & Bishop, W.
Partner: UNT Libraries Government Documents Department
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Design and Development of Fast-Response Thermopile-Type Neutron-Flux- Sensitive Device. Final Report, Phase 2

Description: A program was directed toward development of a thermopile-type neutron- flux-sensitive meter of small physical size and having a fast response time (25 msec) and a high signal output. The meter configuration selected consists essentially of a metallic heat sink, a thermopile, and a thin layer of neutron- sensitive material in series. When the meter is exposed to a neutron environment, heat generated in the neutron-sensitive material flows across the thermopile unit to the heat sink. The signal … more
Date: October 31, 1962
Creator: Gee, L. J.
Partner: UNT Libraries Government Documents Department
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ARGONNE DUAL NEUTRON DIFFRACTOMETERS USING A SINGLE PRIMARY BEAM. Report of Metallurgy Program 4.10.5

Description: Dual neutron diffractometers were designed and built for use at the CP-5 reactor with a number of special features: (1) Two monochromntors are used in an in-line arrangement, as suggested by Levy and Peterson, utilizing the same primary beam with two independent diffractometers, one a horizontal instrument and the other a vertical unit. (2) The two monochromnting crystals may be used in transmission or reflection, and each crystal may be accurntely positioned by external controls. (3) Considera… more
Date: November 1, 1962
Creator: Mueller, M.H.; Heaton, L.; Sidhu, S.S. & Terandy, J.
Partner: UNT Libraries Government Documents Department
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Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. First Quarterly Progress Report, April 1-June 30, 1962

Description: Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The experimental work centers around aspects of detecting neutrons in the presence of 10/sup 7/ r/hr gamma fields. The feasibility of U/ sup 235/ coated solid state detectors for use in these measurements is being studied. A theoretlcal investigation is also in progress on the effects of a multi-region assembly on the fundamental… more
Date: July 1, 1962
Creator: Meyer, Paul & Garelis, Edwin
Partner: UNT Libraries Government Documents Department
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Results of Tensile Tests Performed on Materials Exposed in the Homogeneous Reactor Experiment No. 2 Blanket and Low-Flux-Core Region

Description: Tensile specimens of various alloys of zirconium and titanium and a variety of austenitic stainless steels and Incoloy were exposed in the blanket and low-flux core regions of the Homogeneous Reactor Experiment (HRE) No. 2. The purpose of this exposure was to determine the effect of HRE-2 environment on mechanical properties and to provide corrosion data. Specimens were exposed in the low-flux core region and in two blanket loadings. While the specimens were in the low-flux core region, a maxim… more
Date: October 1, 1962
Creator: Prislinger, J. J.
Partner: UNT Libraries Government Documents Department
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PROTON RECOIL ENERGY LOSS DISTRIBUTION IN PLANE GEOMETRY

Description: Computations of proton recoil energy losses from neutron irradiation of hydrogenous systems possessing plane symmetry were made for the purpose of fast neutron counter design. A digital computer code was written to carry out the calculations for two irradiation geometries: the neutron beam is assumed to be normally incident upon the system, and the system is exposed to an isotropic flux of neutrons. Numerical results are presented for neutrons of various energies incident on plane radiators of … more
Date: July 10, 1962
Creator: Eldridge, H.B.; Flusser, P.R. & Ritchie, R.H.
Partner: UNT Libraries Government Documents Department
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A METALLOGRAPHIC STUDY OF GAS BEHAVIOR IN URANIUM IRRADIATED WITH ALPHA PARTICLES

Description: The behavior of helium in uranium and in several uranium alloys was studied metallographically after room temperature irradiation with alpha particles in a cyclotron, followed by various heat treatments. The observed gas bubbles were classified in two classes, differing in size, concentration, and mechanism of formation. These bubbles appear to resemble those resulting from fission product gases in neutron-irradiated uranium; the findings of this study seem to be applicable to the understanding… more
Date: September 28, 1962
Creator: Green, H.M.
Partner: UNT Libraries Government Documents Department
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Effects of Fast-Neutron Irradiation and High Temperature on Beryllium Oxide

Description: Specimens of 0.428 to 1.18 in. dia. BeO were irradiated at 1.4 x 10/sup 20/ to 2.8 x 10/sup 21/ fast neutrons/cm/ (>1 Mev), with irradiation times of 2.03 x 105 to 5.60 x 106 sec, at 110 to 1025 C, and gamma heat generation rates of 18 to 25 w/g. The greatest damage appeared in bodies irradiated for high neutron doses at low temperatures. Greater doses could be tolerated at higher temperatures. Specimens irradiated at 110 deg C powdered at an accumulated dose of 1.5 x 10/sup 21/ 1.1 x 10/sup 21… more
Date: April 1, 1962
Creator: Shields, R. P.; Lee, J. E., Jr. & Browning, W. E., Jr.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Irradiation of Aqueous Thoria-Urania Slurry at Elevated Temperature. Design and in-Pile Operation of Loop L-2-27S

Description: An in-pile pump loop, designed to fit within horizontal beam hole HB-2 of the Low-Intensity Test Reactor (LlTR), was used to circulate an aqueous thoria- urania slurry while exposed to reactor irradiation. The total loop volume was about 1600 ml, including pump and pressurizer, but the slurry was confined to the 900-ml volume of the main loop stream by means of a sintered stainless steel filter. The filter was an important feature of the loop design in that it provided a thoria-free filtrate as… more
Date: February 14, 1962
Creator: Savage, H. C.; Compere, E. L.; Baker, J. M.; DeCarlo, V. A. & Shor, A. J.
Partner: UNT Libraries Government Documents Department
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Effect of Neutron Irradiation on Materials Subjected to Multi-Axial Stress Distributions. Quarterly Report for the Period Ending June 30, 1962

Description: Activities in a program to determine the effects of neutron irradiation on A-302B steel are reported. Plans are discussed concerning performance tests on tensile, notched tensile, tube, and Charpy specimens. An irradiation capsule design was finalized. A theoretical analysis of the critical conditions arising in a tube subjected to both internal pressure and axial load is included. (J.R.D.)
Date: August 13, 1962
Creator: Trozera, T. A.
Partner: UNT Libraries Government Documents Department
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