2,184 Matching Results

Search Results

Advanced search parameters have been applied.

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

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

Recriticality considerations in LMFBR accidents

Description: From confercnce on fast rea ctor safety; Los Angeles, California, USA (2 Apr 1974). Recent studies suggest that fuel which is dispersed upward by a mild prompt critical burst may reenter the core region causing a secondary excuraion. Several modes of fuel reentry recriticality are examined, and phenomena which strongly affect reactivity ramp rate estimates are evaluated. A broad range of ramp rates results from these studies. The results also indicate that a number of effects expected to be present in realistic situations can strongly mitigate the expected reactivity insertion rates. (29 references) (auth)
Date: January 1, 1974
Creator: Boudreau, J.E. & Jackson, J.F.
Partner: UNT Libraries Government Documents Department

Calculation of nuclear heating rates in LMFBR control rods

Description: The results of calculations of power densities and worths for control rods which use boron for neutron absorption are presented. The calculations were performed as a function of the control assembly core location, axial position, and /sup 10/B enrichment. (JWR)
Date: January 1, 1973
Creator: Gibson, G. & Dyos, M.W.
Partner: UNT Libraries Government Documents Department

Mechanism of liquid--liquid contact and heat transfer related to fuel- coolant interactions

Description: BS>From second specialist meeting on sodium fuel interaction in fast reactors; Ispra-- Varese, Italy (21 Nov 1973). The requirements for explosive boiling (vapor explosion) are discussed with special emphasis on the UO/sub 2/-Na system. Considerations include requirements for direct liquid-liquid contact and associated heat transfer characteristics. Fragmentation and explosive boiling are treated as separate phenomena. (auth)
Date: January 1, 1973
Creator: Fauske, H.K.
Partner: UNT Libraries Government Documents Department

Method of characteristics for pressure transients in cylindrical geometry with axial symmetry: the formulation

Description: The system of governing equations for an unsteady inviscid compressible flow is formulated by the method of characteristics for numerical integration. An axially symmetric cylindrical geometry is considered which simulates a simplified geometry of steam generators. The resulting reduced equations, the bicharscteristic and compatibility equations involve one less independent variable than the original system of equations. The system of governing partial differential equations if reduced to a system of integral equations written along bicharacteristics. Numerical integration can be performed either using the compatibility relations by writing in finite differences or using the system of integral equations by various approximation techniques. (11 references) (auth)
Date: October 1, 1973
Creator: Shin, Y.W.
Partner: UNT Libraries Government Documents Department

Sodium technology, 1972--1973

Description: References to 897 publications on sodium and NaK technology cited in Nuclear Science Abstracts Volume 26 (1972) through Volume 27 (1973 through June) are contained in this bibliography. Keyword indexing is displayed under each 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: February 1, 1974
Partner: UNT Libraries Government Documents Department

End to hypothetical safety

Description: From conference on fast reactor safety; Los Angeles, California, USA (2 Apr 1974). It is shown that the design of safety features for hypothetical accidents in LMFBR's has in some cases detracted from the real functional safety of the plants. An alternative approach to the question of safety in LMFBR's is suggested. (JWR)
Date: January 1, 1973
Creator: Graham, J.
Partner: UNT Libraries Government Documents Department

Compilation of data and descriptions for United States and foreign liquid metal fast breeder reactors

Description: This document is a compilation of design and engineering information pertaining to liquid metal cooled fast breeder reactors which have operated, are operating, or are currently under construction, in the United States and abroad. All data has been taken from publicly available documents, journals, and books. (auth)
Date: August 1, 1975
Creator: Appleby, E.R.
Partner: UNT Libraries Government Documents Department