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Liquid metal fast breeder reactors, 1972--1973

Description: Reference to 1467 publications on liquid sodium fast breeder reactors cited in Nuclear Science Abstracts Volume 26 (1972) through Volume 27 (1973 through June) are contained in this citation to provide information on the contents of the document. References are arranged in order by the original NSA abstract number which approximately places them in chronological order. Sequence numbers appear beside each reference, and the personal author index refers to these sequence numbers. The subject index refers to the original abstract numbers. (auth)
Date: January 1, 1974
Partner: UNT Libraries Government Documents Department

Experimental evaluation of fission-gas release in LMFBR subassemblies using an electrically heated test section with sodium as coolant

Description: A description is given of an out-of-pile experiment which simulated fission-gas release in current-design uranium-oxide fuel subassemblies of liquid- metal-cooled fast breeder reactors (LMFBR's) and which was performed to evaluate the potential for pin-to-pin failure propagation due to thermal transients induced in adjacent fuel pins. A sodium-cooled test section containing three electrically heated pins was used. Gas (angon or xenon), injected as a jet through a needle protruding into the flow cross-sectional area of the test section, was made to impinge on one of the heater pins. Data are presented regarding the measured cladding-temperature rise and the calculated local heat- transfer coefficient in the impingement area, with the following parameters: gas type, needle internal diameter, heat flux, coolant flow rate, gas-plenum pressure and temperature, and axial location with respect to the gas jet. The cladding- temperature rises measured represent upper values, since the conditions under which they were obtained are conservative. There are two reasons for this: (a) The gasrelease rates correspond to those that would prevail if the internal resistance to the flow of gas, between the gas plenum and the point of release of the fuel pin, were negligibly small; (b) the tests were performed under steady- state conditions, whereas, under actual reactor conditions, the gas-release rates would be decreasing with time because of the fixed fission-gas inventory. For a narrow range of gas-release rates under subsonic and near-subsonic conditions, cladding-temperature rises were found to occur in the impingement area, for the above conservative conditions, of up to approximates 240 deg C at a heat flux of 250 W/cm/sup 2/. (auth)
Date: July 1, 1973
Creator: Wilson, R.E.; van Erp, J.B.; Chawla, T.C.; Kimont, E.L. & Baldwin, R.D.
Partner: UNT Libraries Government Documents Department

Under sodium viewing

Description: From IEEE ultrasonics symposium; Monterey, California, USA (5 Nov 1973). Under sodium viewing combines some standard ultrasonic techniques with some new dnta processing methods to perform ranging and imaging fanctions in the optically opaque coolant of the Liquid Metal Fast Breeder Reactor. Pulse-echo scanning methods including both B-scan and C-scan are used in conjunction with a synthesis of these methods by a technique called ISO-SCAN. by combining depth and spatial information from the B- and Cscans, ISO-SCAN produces a 3-dimensional visualization of objects submersed in liquid sodium. Special transducers have been developed to operate in sodium at temperatures up to 550 deg F. This developm ent included a process for promoting rapid wetting of the tainless steel lens of the transducer by the sodium. A lack of wetting prevents acoustic coupling between the transducer and sodium. Experiments conducted in sodium to 600 deg F have demonstrated the ability to locate and identify objects. (auth)
Date: October 1, 1973
Creator: Day, C.K. & Smith, R.W.
Partner: UNT Libraries Government Documents Department

Electromagnetic self-excitation effects in liquid metal cooled reactors

Description: For Westinghouse Hanford Co., Richland, Wash. Electromagnetic self- excitation effect is a posaible problem in LMFBR's. Geometry and flow parameters may rule it out; the magnetic Reynolds number criterion does not. The components in which the electromagnetic self-excitation effect may occur in liquid metal loops are analyzed. The conditions required for the occurrence of the effect and its consequences are described. (auth)
Date: December 1, 1973
Creator: Lessor, D.L.
Partner: UNT Libraries Government Documents Department

Status of LMFBR Reheat in Western Europe--1972: Report of the United States of America LMFBR Sodium Reheat Team Visit to France , Germany (FRG), Netherlands, and United Kingdom, May 22-June 6, 1972

Description: From summary: This report describes the trips to Western European countries designing and constructing LMFBR demonstration plants for the purpose of determining the directions being taken by these countries to provide acceptable quality steam to commercially available steam turbines.
Date: March 1973
Creator: Weber, Max
Partner: UNT Libraries Government Documents Department

Post test valve examination of Sargent Globe valve

Description: The examination was made to observe and record any abnormalities caused by verification testing in liquid sodium which simulated 20 years of reactor service in FFTF and LMFBRs. The test program consisted of gas leakage measurements before and after a series of closing and opening actuations and thermal transient cycle exposures. External loads were used to simulate flow-induced vibration. Recommendations are given for applying these valves to future sodium systems. (23 figures) (DCL)
Date: March 1, 1977
Creator: Funk, C.W.
Partner: UNT Libraries Government Documents Department