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January 1978 monthly highlights for Office of Nuclear Regulatory Research Programs at Oak Ridge National Laboratory

Description: Highlights of technical progress during January 1978 are presented for sixteen separate program activities which comprise the ORNL research program for the Office of Nuclear Regulatory Research's Division of Reactor Safety Research.
Date: February 10, 1978
Creator: Mynatt, F.R. (comp.)
Partner: UNT Libraries Government Documents Department

Testimony (on space nuclear power) before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives

Description: This brief presentation consists of four parts: first, a few introductory comments about space nuclear power technology; second, a description of activities currently underway at Martin Marietta Energy Systems; third, a discussion of future directions at Martin Marietta Energy Systems; and fourth, some recommendations.
Date: October 9, 1985
Creator: Mynatt, F.R.
Partner: UNT Libraries Government Documents Department

Application of the FORSS sensitivity code system to fast reactor analysis

Description: The FORSS Sensitivity Analysis Code System is described in terms of its objectives and present capabilities. An example is made of a problem specified by the Processing Methods Testing Subcommittee of the Code Evaluation Working Group, i.e., the determination of integral parameters, sensitivities to cross- section data, methods and data uncertainties, and required cross-section accuracies for an infinite media of ZPR 6/7 core composition. (auth)
Date: October 22, 1975
Creator: Weisbin, C.R.; Oblow, E.M. & Mynatt, F.R.
Partner: UNT Libraries Government Documents Department

Methods for U. S. shielding calculations: applications to FFTF and CRBR designs

Description: The primary components of the U.S. reactor shielding methodology consist of: (1) computer code systems based on discrete ordinates or Monte Carlo radiation transport calculational methods; (2) a data base of neutron and gamma-ray interaction and gamma-ray-production cross sections used as input in the codes; (3) a capability for processing the cross sections into multigroup or point energy formats as required by the codes; (4) large-scale integral shielding experiments designed to test cross-section data or techniques utilized in the calculations; and (5) a ''sensitivity'' analysis capability that can identify the most important interactions in a transport calculation and assign uncertainties to the calculated result that are based on uncertainties in all of the input data. The required accuracy for the methodology is to within 5 to 10% for responses at locations near the core to within a factor of 2 for responses at distant locations. Under these criteria, the methodology has proved to be adequate for in-vessel LMFBR calculations of neutron transport through deep sodium and thick iron and stainless steel shields, of neutron streaming through lower axial coolant channels and primary pipe chaseways, and of the effects of fuel stored within the reactor vessel. For ex-vessel LMFBR problems, the methodology requires considerable improvement, the areas of concern including neutron streaming through heating and ventilation ducts, through the cavity surrounding the reactor vessel, and through gaps around rotating plugs in the reactor heat, as well as gamma-ray streaming through plant shield penetrations.
Date: January 1, 1978
Creator: Engle, W.W. Jr.; Mynatt, F.R. & Disney, R.K.
Partner: UNT Libraries Government Documents Department

ORNL (Oak Ridge National Laboratory) 89

Description: This is the inaugural issues of an annual publication about the Oak Ridge National Laboratory. Here you will find a brief overview of ORNL, a sampling of our recent research achievements, and a glimpse of the directions we want to take over the next 15 years. A major purpose of ornl 89 is to provide the staff with a sketch of the character and dynamics of the Laboratory.
Date: January 1, 1989
Creator: Anderson, T.D.; Appleton, B.R.; Jefferson, J.W.; Merriman, J.R.; Mynatt, F.R.; Richmond, C.R. et al.
Partner: UNT Libraries Government Documents Department