Resource Type
Serial/Series Title
NACA Research Memorandums
162
Atomic Energy Commission Reports
52
NACA Technical Reports
35
Oak Ridge National Laboratory Reports
23
Hanford Works Reports
22
University of California Radiation Laboratory Reports
15
HW (Series)
14
ORNL (Series)
9
BNL (Series)
7
Brookhaven National Laboratory Reports
7
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339 Matching Results
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High Power Density Development Project: Interim Report, 300 MWe HPD Conceptual Design Study
From introduction: "Preliminary design and analysis of the 300 MWe core."
Date:
January 5, 1962
Creator:
Grayhek, V. G.
Object Type:
Report
System:
The UNT Digital Library
Program For the Development of Plutonium Recycle For Use in Light Water Moderated Reactors: Third Quarterly Report
This is a report of work completed during the period October 1, 1961, to December 31, 1961. The Program fuel element was completed and assembled. After extensive analysis, it was concluded that the fuel was satisfactory for use in the Program.
Date:
January 5, 1962
Creator:
Carver, J. G.
Object Type:
Report
System:
The UNT Digital Library
A Study of the Feasibility of Using Scintillating Fibers for Low Energy Beta Counting: Quarterly Report Number 1, June - September 1961
From introduction: "A detector system with the advantages of a liquid counter, but without the severe requirements on sample preparations, has been devised and is the basis of the present experimental investigation."
Date:
January 5, 1962
Creator:
Preston, C.
Object Type:
Report
System:
The UNT Digital Library
Electrical Limitations To Energy Resolution In Semiconductor Particle Detectors
Based on the assumption that the noise contribution of a semiconductor detector is due solely to the bulk properties of the semiconductor, equations are presented which indicate the theoretical limits of noise in detector-amplifier combinations. These equations show that an optimum amplifier time constant and detector bias voltage exist for which condition the minimum noise is independent of the semiconductor resistivity. The optimum performance of a detector-amplifier system is shown to depend only upon detector area, input capacity (less detector capacity), semiconductor minority carrier lifetime, and the transconductance of the amplifier input tube. A new detector structure including a guard-ring electrode as an integral part of the detector structure is described which largely eliminates noise due to surface leakage. Experimental results for detector leakage and energy resolution are presented which agree well with theory.
Date:
April 5, 1961
Creator:
Hansen, William L. & Goulding, Frederick S.
Object Type:
Report
System:
The UNT Digital Library
Improved Zirconium Alloys : Ninth Monthly Report Covering the Period December 1 to December 31, 1960
The following report is the ninth in a series of monthly reports covering the program with the objective of developing alloys having superior 680 F water and/or 750 to 900 F steam corrosion resistance, as well as developing higher strength alloys for current temperature ranges while still maintaining corrosion resistance comparable to that of Zircaloy-2. This report was made covering the period December 1 to December 31, 1960.
Date:
January 5, 1961
Creator:
Weinstein, Daniel & Van Thyne, R. J.
Object Type:
Report
System:
The UNT Digital Library
Preparation of Thin, Self-supporting Copper Films
A repeatable technique for preparation of thin, self-supporting copper films has been developed at the Lawrence Radiation Laboratory in Livermore, California. The process, done in a vacuum chamber, involves evaporation of copper by electron bombardment, and deposition of the copper on a detergent-coast glass substrate. The copper film is later removed from the substrate by immersion in water.
Date:
January 5, 1961
Creator:
Brunner, W. & Patton, H.
Object Type:
Report
System:
The UNT Digital Library
Research Study on Neutron Interactions in Matter as Related to Image Formation
Report discussing a study on neutron detection schemes and the effect of neutron scattering on neutron image formation quality.
Date:
December 5, 1960
Creator:
Watts, H. V. & Stone, C. A.
Object Type:
Report
System:
The UNT Digital Library
Strontium Sorption Studies Using Naturally Occurring Ion Exchange Materials
Four naturally occurring materials, namely, vermiculite, variscite, Tennessee rock phosphate, and Florida pebble phosphate, were studied to determine the feasibility of their use in columns for the sorption of strontium from high pH, intermediate-level wastes produced at ORNL. Excepting vermiculite, all materials were found to be effective in strontium removal.
Date:
December 5, 1960
Creator:
Thomas, K. T.; Jacobs, D. G.; Tamura, T. & Struxness, E. G.
Object Type:
Report
System:
The UNT Digital Library
A Transport Calculation of the HFIR Beam Hole Currents
An estimate was made of the beam hole currents to be expected from both the radial and tangential beam holes in the present HFIR design. The angular fluxes required for these calculation were determined by an 18-group, S8 transport calculation (SNG reactor code). Both type beam holes produced thermal neutron currents of 7.5 x 10^10 neutrons/cm^2 sec. at a power level of 100 Mw. The nonthermal component of the beam current was 7.0 x 10^10 and 4.5 x 10^10 neutrons/cm^2 -sec for the radial and tangential holes, respectively.
Date:
December 5, 1960
Creator:
Claiborne, H. C. & Rakavy, G.
Object Type:
Report
System:
The UNT Digital Library
Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I
Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II and SM-1A Core I contain nearly identical B-10 loading of 17.79 grams, compared to the best estimate of 15.75 grams for SM-1 Core I. The available data indicates that all three cores possess similar nuclear characteristics.
Date:
October 5, 1960
Creator:
Paluszkiewicz, S.
Object Type:
Report
System:
The UNT Digital Library
EURATOM PROGRAM "Improved Zirconium Alloys"
Introduction: "This report is an expanded version of the regular monthly letter report and is prepared in this form with the intention of reviewing work on the subject program for Euratom technical personnel. Work performed during the month of September, which normally constitutes the entire letter report, has been condensed under one heading."
Date:
October 5, 1960
Creator:
Weinstein, Daniel & Van Thyne, R. J.
Object Type:
Report
System:
The UNT Digital Library
Summary of Gummed Film Results Through December, 1959
From Abstract: "The data for gummed film fallout measurements through December 1959 are reported. The bulk of the report consists of summary tables for each gummed film station listing the monthly estimates of strontium 90 deposition and infinity gamma dose."
Date:
September 5, 1960
Creator:
Harley, John H.; Hallden, Naomi A. & Ong, Long D. Y.
Object Type:
Report
System:
The UNT Digital Library
The Boron-Carbon System: Quarterly Report Number 1, May - June 1960
Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. Alloys are being produced by sintering pressed powder aggregates with subsequent arc melting. Alloys have been made at two atomic percent intervals up to thirty atomic per cent carbon. In the future, higher carbon compositions are to be investigated. Techniques have been worked out for the metallographic preparation of the extremely hard and friable alloys.
Date:
August 5, 1960
Creator:
Elliott, Rodney P. & Van Thyne, R. J.
Object Type:
Report
System:
The UNT Digital Library
PM-1 Nuclear Power Plant Program: 5th Quarterly Progress Report, March 1, 1960-May 31, 1960
From abstract: Reactor development work includes: initiation of the flexible zero-power test (PMZ-1) experimental program, fabrication and delivery of a PM-1 type fuel element, continuation of reactor flow and heat transfer tests, development work on rare earth control rods, and testing and redesign of the prototype magnetic jack-type control rod actuator.
Date:
July 5, 1960
Creator:
Martin Company. Nuclear Division.
Object Type:
Report
System:
The UNT Digital Library
A Study of the Wear and Galling of Autoclaved Zircaloy-2 By Various Materials
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 element support-bearing surface materials.
Date:
July 5, 1960
Creator:
Weber, J. W.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Aluminum for use in Reactors Cooled by High-Temperature Recirculating Water
aluminum has been considered as a material for cladding fuel elements to be used in reactors cooled by high-temperature recirculating water. Aluminum is abundant, chap, has a relatively low cross section for thermal neutrons, and is readily fabricated into complex shapes. For these reasons, it appears that the use of aluminum rather than steel, Zircaloy or other candidate materials for fuel element cladding, would result in considerable savings in operating expense. The actual economics will of course depend on specific factors such as core materials and design of the reactor/. Aluminum appears particularly attractive for cladding the cores of aluminum-plutonium alloy proposed for the Plutonium Recycle Test Reactor since, in this case, the physical characteristics of the core and cladding would be practically identical.
Date:
April 5, 1960
Creator:
Ayres, J. A.
Object Type:
Report
System:
The UNT Digital Library
PM-1 Nuclear Power Plant Program: 4th Quarterly Progress Report, December 1, 1959-February 29, 1960
From abstract: The principal efforts during the fourth project quarter were the near-completion of the final design and preparation of specifications for plant components. Reactor development work included final preparations for the flexible zero-power test (PMZ-1) program and revised fuel element irradiation test program, continuation of reactor flow test, further work on heat transfer test program, and final design and fabrication of the prototype magnetic jack-type control rod actuators.
Date:
April 5, 1960
Creator:
Martin Company. Nuclear Division.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Fretting Corrosion of ZR-2
Although the corrosion of resistance of Zircaloy--2 clad fuel elements in high temperature water is excellent, some concern has been expressed in regard to the resistance against fretting corrosion. Since this form of corrosion can proceed quite rapidly it could induce fuel element failure through penetration of the cladding. Fretting corrosion if it occurred, would take place either where the fuel element contacted the process tube or where portions of the fuel element contacted each other, e. g. wire-wrapping around a cluster of cylindrical fuel rods. This form of corrosion is defined as corrosion occurring at contact areas and as such, fretting of Zircaloy-2 could take place in many reactor concepts. This report details the results of testing performed to induce fretting corrosion of Zircaloy-2 and the direction of the future tests.
Date:
February 5, 1960
Creator:
Lobsinger, R. J.
Object Type:
Report
System:
The UNT Digital Library
KAPL-120-8A Test Assembly Thermocouple Failure.
This document reports the circumstances surrounding the failure of sheathed thermocouples during a test being conducted in the KAPL-120 Loop. The report is prepared to provide a record of these events and to acquaint those who use these thermocouples for testing of other applications with the difficulties that are sometimes encountered.
Date:
February 5, 1960
Creator:
Dearing, F. E.
Object Type:
Report
System:
The UNT Digital Library
Ionization Equilibrium Equation of State
Abstract: "A simple solution to Saha's equation has been obtained. The method of solution involves iteration with respect to the electron pressure or concentration and can be applied to the simultaneous calculations of any number of ions. Sample results are given for lithium and aluminum."
Date:
October 5, 1959
Creator:
Rouse, Carl A.
Object Type:
Report
System:
The UNT Digital Library
Calculation of Transport Cross Sections
Many elements exhibit anisotropic scattering at energies of interest in reactor calculations. A method is presented for the calculation of transport cross sections including the observed anisotropy.
Date:
August 5, 1959
Creator:
Nestor, C. W.
Object Type:
Report
System:
The UNT Digital Library
Chemical Development Section C Monthly Progress Report July 1959
Nitrate contained in raffinates from Canadian Blind River mills interferes seriously with thorium extraction by secondary amines. With primary amines, however, the effect is negligible and these compounds are the preferred process extractants.
Date:
August 5, 1959
Creator:
Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Ryon, A. D. et al.
Object Type:
Report
System:
The UNT Digital Library
A Closed Circuit Television System for In-Well Use -- Interim Report
Wells drilled to date on the Hanford project represent and initial investment of over one million dollars. These nearly six hundred wells have been used and will continue to be used for observation and monitoring purposes of direct interest to ground disposal of radioactive wastes. Through measurement of depth to the water table the changing gradients as a result of large volume waste disposal are determined and direction of ground water flow established. The extent of contamination in ground water is measured in samples dawn from these wells. Aquifer permeability is measured and ground water velocity predicted from pumping tests carried out out in these structure
Date:
August 5, 1959
Creator:
Ratcliffe, C. A.
Object Type:
Report
System:
The UNT Digital Library
Temperature and Rate of Heat Removal of UO2 Test Elements
The method of calculation of various quantities relating the temperature and the rate of heat removal of UO2 test elements is presented. Graphs of the appropriate quantities as a function of the rate of heat removal are included.
Date:
August 5, 1959
Creator:
Perry, A. M.
Object Type:
Report
System:
The UNT Digital Library