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SHIELD DESIGN METHODS FOR ARGONAUT-TYPE REACTORS

Description: The methods used in calculating the shielding for Argonaut type reactors are described. The shield designs for the Argonaut-1 Reactor and the.Argonaut Reactor were investigated. The methods used appeared to be satisfactory within the anticipated limits of accuracy. (auth)
Date: March 1, 1960
Creator: Fagan, J.
Partner: UNT Libraries Government Documents Department

SUMMARY OF THE FFAG05 WORKSHOP AT KEK.

Description: The FFAG05 workshop at KEK is one in a series of important annual gatherings of scientists working in the area of fixed field alternating gradient accelerators (FFAGs). At this workshop, we heard of many FFAG designs that are in operation, under construction, and in the planning stages. These machines are being used for a wide variety of applications. We also had a great deal of discussion of some of the theoretical aspects of FFAG design. This paper attempts to give a coherent summary of the workshop, and hopefully serves as an introduction to the more detailed papers in the workshop proceedings.
Date: January 30, 2006
Creator: BERG, J.S.
Partner: UNT Libraries Government Documents Department

AMPLITUDE DEPENDENCE OF TIME OF FLIGHT.

Description: Machida found in tracking studies [Shinji Machida, presentation at the FFAG05 Workshop, Kyoto University Research Reactor Institute, Osaka, Japan, 5-9 December 2005] that the time of flight in a linear non-scaling FFAG depended on the transverse amplitude of the particles. I compute a relationship between the transverse amplitude dependence of the time of flight and the variation of tune with energy and explain its physical origin.
Date: January 30, 2006
Creator: BERG, J.S.
Partner: UNT Libraries Government Documents Department

SHUT-DOWN COOLING OF ORR

Description: Information is presented that may be used in estimating the magnitude of the shutdown cooling problem in the ORR at various power levels. The information used in the investigation was obtained from other research reactors. (W.L.H.)
Date: August 14, 1959
Creator: Cole, T.E.
Partner: UNT Libraries Government Documents Department

PROCEEDINGS OF THE AEC SYMPOSIUM FOR CHEMICAL PROCESSING OF IRRADIATED FUELS FROM POWER, TEST, AND RESEARCH REACTORS, RICHLAND, WASHINGTON, OCTOBER 20 AND 21, 1959

Description: A review is presented in this symposium of the technology currently available for processing spent fuels from research, test, and power reactors. Twenty-one papers are included. Separate abstracts have been prepared for each paper. (W.L.H.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department

IN-PILE MECHANICAL FAILURE OF MTR FUEL ASSEMBLIES

Description: Fuel assembly failures that have occurred as the result of mechanical deficiencies of the assemblies are described. The causes of the failures are analyzed, and measures taken to avoid additional failures are described. (D.C.W.)
Date: July 1, 1963
Creator: Harrison, L.J.
Partner: UNT Libraries Government Documents Department

The Development of Mobile Melt-Dilute Technology for the Treatment of Former Soviet Union Research Reactor Fuel

Description: On-site application of the MMD process offers an economical method for converting weapons usable Former Soviet Union (FSU) High Enriched Uranium (HEU) research reactor fuel to a safe and secure Low Enriched Uranium (LEU) ingot. The objective of the MMD Project is to develop the mobile melt and dilute technology in preparation for active equipment deployment in the Newly Independent States (NIS) of the FSU.
Date: October 9, 2003
Creator: Adams, T.
Partner: UNT Libraries Government Documents Department

Time delays between core power production and external detector response from Monte Carlo calculations

Description: One primary concern for design of safety systems for reactors is the time response of external detectors to changes in the core. This paper describes a way to estimate the time delay between the core power production and the external detector response using Monte Carlo calculations and suggests a technique to measure the time delay. The Monte Carlo code KENO-NR was used to determine the time delay between the core power production and the external detector response for a conceptual design of the Advanced Neutron Source (ANS) reactor. The Monte Carlo estimated time delay was determined to be about 10 ms for this conceptual design of the ANS reactor.
Date: August 1, 1996
Creator: Valentine, T. E. & Mihalczo, J. T.
Partner: UNT Libraries Government Documents Department

ADMINISTRATION OF ORNL RESEARCH REACTORS

Description: Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)
Date: August 20, 1962
Creator: Casto, W. R.
Partner: UNT Libraries Government Documents Department

Greenfield Alternative Study LEU-Mo Fuel Fabrication Facility

Description: This report provides the initial “first look” of the design of the Greenfield Alternative of the Fuel Fabrication Capability (FFC); a facility to be built at a Greenfield DOE National Laboratory site. The FFC is designed to fabricate LEU-Mo monolithic fuel for the 5 US High Performance Research Reactors (HPRRs). This report provides a pre-conceptual design of the site, facility, process and equipment systems of the FFC; along with a preliminary hazards evaluation, risk assessment as well as the ROM cost and schedule estimate.
Date: July 1, 2008
Creator: URS, Washington Division of
Partner: UNT Libraries Government Documents Department

ARGONNE HIGH-FLUX RESEARCH REACTOR-AHFR CONCEPTUAL DESIGN STUDY

Description: This report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiations in thermal neutron flux approaching 5 x 10/sup 15/n/ (cm/sup 2/ )(sec) and some beam experiments having over 10/sup 15/ n/(cm/sup 2/) available. Parametric studies indicate that the highest peak thermal flux per unit of reactor power can be obtained in an internal H/sub 2/ reflector having a radius of about 6 cm. Since the design effonts recognized total reactor cost as a mator parameter, an all H/sub 2/O-cooled system was adopted as most expedient. Further, the design and calculations effont was directed toward operating conditions which require little or no research effort. This latter point is a recognition both of the over-all cost plus a desire to meet the needs of research in the shortest possible time. (auth)
Date: June 1, 1959
Creator: Link, L.E.; Armstrong, R.H.; Cameron, T.C.; Heineman, J.B.; Kelber, C.N.; Kier, P.H. et al.
Partner: UNT Libraries Government Documents Department