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Guidelines to Achieve Seals with Minimal Leak Rates for HWR-NPR Coolant System Components

Description: Existing technology for seal systems was reviewed with regard to flange, elastomer, valve, and pump design. A technology data base for the designers of the HWR-NPR coolant system was derived from operating experience and seal development work on reactors in the United States, Canada, and Europe. This data base was then used to generate guidelines for the design of seals and/or joints for the HWR-NPR coolant system. Also discussed are needed additional research and development, as well as the necessary component qualification tests for an effective quality control program.
Date: March 1991
Creator: Finn, P. A.
Partner: UNT Libraries Government Documents Department

General Flattening and Power Curves

Description: Introduction: "In the evaluation of pile designs it is necessary to know how the production varies with the number of tubes. It has been possible to solve the problem in terms of some general parameters whose values may be quickly computed for any specific design when the pertinent information is available."
Date: March 30, 1953
Creator: Gast, Paul F.
Partner: UNT Libraries Government Documents Department

Notes on Degradation of Heavy Water Moderator by Ion Exchange Beds and Metal Surfaces

Description: Abstract: "Data on the isotopic degradation of heavy water used to deuterize deionizer beds at Savannah River Plant are presented. Also, the extent to which light hydrogen, chemically bound to aluminum surfaces may degrade heavy water is estimated."
Date: 1957
Creator: U.S. Atomic Energy Commission. Savannah River Operations Office.
Partner: UNT Libraries Government Documents Department

Preliminary Evaluation of Licensing Issues Associated with U. S.-Sited CANDU-PHW Nuclear Power Plants

Description: The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S.
Date: December 1977
Creator: van Erp, Jan B.
Partner: UNT Libraries Government Documents Department

Dependence of Thermal Utilization and Resonance Escape Probability Upon Fuel Element Density in D₂O Cooled and Moderated Systems

Description: Abstract: "The effect of variation in fuel element density upon f, p in a D2O cooled and moderated lattice of cylindrical fuel elements is investigated. The CP-3 lattice is chosen as a reference. The effect of a source term in the fuel element is considered. f, p are calculated as functions of "a", the ratio of the modified fuel element density to the original (fuel only) density. Curves showing f(a), p(a) are included. It is concluded that a 1 per cent decrease in the product, f(d), p(a) is not suffered until a=0.3. A 5 per cent decrease in k is estimated at a-0.4. The necessity of introducing the fuel element source term into the calculation after a has been decreased to about 0.6 is brought out."
Date: April 23, 1952
Creator: Garvey, J. E. & Stevens, T.
Partner: UNT Libraries Government Documents Department

CIVILIAN POWER REACTOR PROGRAM. PART II. ECONOMIC POTENTIAL AND DEVELOPMENT PROGRAM. HEAVY WATER-MODERATED POWER REACTOR

Description: The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel development program, and improvements which would result from the successful completion of the development program as presented. One plant size was used in the evaluation of plant potential, with a 300 Mw/sub e/ nominal rating. The boiling D/sub 2/O-cooled, pressure tube direct cycle plant design was used. The current development program is outlined; this work includes several items leading to the long-range development of the concept. (auth)
Date: August 19, 1960
Creator: Hutton, J.H.; Davis, S.A.; Graves, C.C. & Duffy, J.G. comps.
Partner: UNT Libraries Government Documents Department