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1,835 Matching Results
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Plasma Accumulation in a Device Fed by Energetic Ion Trapping
Simon (1960) has given a general steady state theory of plasma accumulation (without energy losses) in an OGRA device. Such a device is fed by injection of energetic molecular ions which dissociate to produce trapped protons. Initial trapping is achieved by dissociation in the background gas. Such a device is usually characterized by a critical input current of critical plasma density (a function of input current) above which plasma density builds up to a value limited by Coulomb-scattering losses. For a regime of operation of current interest at Oak Ridge National Laboratory (600-kev hydrogen molecular ion injection and dissociation, highly efficient ion-pumping action of the trapped plasma), extremely simple approximate formulas have been derived which describe with a fair degree of accuracy the critical current of density for plasma build-up.
Date:
November 10, 1960
Creator:
Mackin, R. J., Jr.
Object Type:
Report
System:
The UNT Digital Library
Equipoise-2: A Two-Dimensional, Two-Group, Neutron-Diffusion Code for the IBM-7090 Computer
Equipoise-2, a two-dimensional, two-group neutron-diffusion code in R-Z geometry, has been programmed for the IBM-7090 computer. This code was designed to permit the running of large numbers of cases without requiring excessive machine time. Typical running times are of the order of one to three minutes per case for a 1000-point problems. The maximum number of mesh points that can be used is 1444.
Date:
November 21, 1960
Creator:
Fowler, T. B. & Tobias, Melvin
Object Type:
Report
System:
The UNT Digital Library
Experimental Determination of an Adequate Fission Chamber Location in the ORR Pool
An experiment was performed at the ORR in order to find a good fission chamber location. Two locations on the pool side of the reactor tank were explored with a one inch diameter fission chamber. The thermal neutron flux attention was found to vary nearly exponentially with distance, and no shadowing effect could be seen during a reactor startup. The fission products high gamma flux could be discriminated without difficulties. Both positions seem to be adequate to locate a reactor control fission channel.
Date:
November 4, 1960
Creator:
Roux, D. P. & Colomb, A. L.
Object Type:
Report
System:
The UNT Digital Library
Analog Study of the Reference Design of the Gas-Cooled ORR Loop No. 1
A stimulation study of the deign as of June 1960 of the gas-cooled ORR Loop No. 1 was made using the ORNL analog computer. The proposed method of temperature control is evaluated, and the dynamic behavior of the loop for accidents and component failures is presented in graphical form.
Date:
November 8, 1960
Creator:
Ball, S. J.
Object Type:
Report
System:
The UNT Digital Library
Design and Development of a High-Temperature High-Pressure Spectrophotometer System: Status Report
On 3/14/60 the Applied Physics Corporation was awarded a subcontract for the design and development of a high-temperature high-pressure spectrophotometer system based on the Cary Model 14pm Spectrophotometer insofar as possible, and consistent with our specifications, No. CTD-2, December 16, 1959.
Date:
November 12, 1960
Creator:
Biggers, R. E. & Wymer, R. G.
Object Type:
Report
System:
The UNT Digital Library
Analog Stimulation of HRP In-Pile Slurry Loop Facility in the LITR
An analog simulation is made of the HRP in-pile slurry loop in the LITR. The radiolytic gas pressure in the pressurizer is determined. This pressure is a result of the generation of radiolytic gas in the loop core. A graphical result is obtained showing the effect of catalyst activity and pressurizer flow rate on the pressure rise from radiolytic gas. The thermal behavior of the system is studied, and the response to various controller settings is predicted. Controller settings very near optimum for the actual process were recommended from the analog study,
Date:
November 28, 1960
Creator:
Hinton, D. B.
Object Type:
Report
System:
The UNT Digital Library
Conceptual Design and Economic Evaluation of a Steam-Cooled Fast Breeder Reactor
From abstract: This report describes a conceptual design and economic evaluation of 300 and 40 MWe steam-cooled fast breeder reactor power plants performed by NDA under contract with the AEC.
Date:
November 15, 1961
Creator:
Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
Object Type:
Report
System:
The UNT Digital Library
Paper Presented by M. Minashin
The attached paper is a translation of a rough draft of the paper, "Operating Experience of the APS-1", presented by M. Minashin in Russian at the IAEA Conference on Small and Medium Power Reactors, Vienna, Austria, September 5-9, 1960.
Date:
November 1, 1960
Creator:
Ullmann, J. W. & Gerrrard, Martha
Object Type:
Report
System:
The UNT Digital Library
The DF-4 Fuel Damage Experiment in ACRR With a BWR Control Blade and Channel Box
"In addition to BWR background information, this document contains a description of the experimental hardware with details on how the experiment was instrumented and diagnosed, a description of the test progression, and a presentation on the on-line instruments."
Date:
November 1989
Creator:
Gauntt, Randall Owen; Gasser, R. D. & Ott, L. J.
Object Type:
Report
System:
The UNT Digital Library
Appendix D: The DF-4 Control Blade/Channel Box Guel Damage Experiment
Graphs presenting measured data for the DF-4 control blade/channel box fuel damage experiment including a graphical representation of each of the on-line measured data quantities.
Date:
November 1989
Creator:
Gauntt, Randall Owen; Gasser, R. D. & Ott, L. J.
Object Type:
Dataset
System:
The UNT Digital Library
Radioactivation Analysis
The development of nuclear reactors and other nuclear particle sources has given the analyst a new analysis method which can be successfully applied to the determination of microgram and submicrogram quantities of many elements. Known as "radioactivation analysis", this method is one in which an "activation" by some type of nuclear reaction is used to produce a radioactive isotope of the element to be determined. Since this radioisotope decays with its own characteristic radiations and half-life, it is possible to make radioactivation analysis a very specific analysis. Chemical separations of the radioisotope are employed whenever necessary and its radioactivity measured by some type of radiation counter.
Date:
November 30, 1960
Creator:
Leddicotte, G. W.
Object Type:
Report
System:
The UNT Digital Library