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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

Flow transients in CLIRA and TSMDA

Description: From joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition; San Francisco, California, USA (11 Nov 1973). The capability of the Closed Loop In-Reactor Assembly (CLIRA) in FFTF to accommodate various postulated events is demonstrated. These events include, in their order of severity, (a) flow coastdown, (b) inlet pipe break, and (c) inlet blockage. All of these accidents are extremely unlikely, nonetheless the consequences of even the most severe flow-transient accident is shown to cause no failure propagation to the reactor, even if a Test Section Meltdown Accident (TSMDA) should result. (auth)
Date: April 30, 1974
Creator: Agrawal, A.K.; Hoppner, G.; Coffield, R.D. & Bradbury, P.
Partner: UNT Libraries Government Documents Department

Influence of control rod worth interactions on LMFBR control systems design

Description: These design criteria are interpreted to define the reactivity worth requirements for the primary and secondary control systems in terms of the minimum control systems capability under faulted conditions which will assure that the reactor can be safely shut down. The faulted conditions are postulated to occur upon the simultaneous failure of one of the redundant safety control systems to scram, a stuck rod in the scramming system, and a reactivity insertion resulting from the uncontrolled withdrawal of the highest worth control rod inserted in the reactor. The resulting positive reactivity insertion from the rod runout envelopes other postulated operational faults and is imposed on the shutdown requirements of both the primary and secondary control systems. In order to determine the minimum shutdown capability, an evaluation is made of the worst combination of control rod runout (reactivity fault) and stuck rod worth.
Date: January 1, 1980
Creator: Lake, J.A.; Rittenberger, R.V. & Rathbun, R.W.
Partner: UNT Libraries Government Documents Department

Simplified design methods for nonlinear dynamic mechanical systems

Description: Dimensional analysis and classical methods are combined in a novel way to develop a simplified mathematical description of two practical nonlinear dynamic mechanical systems experiencing excitation similar to that due to an earthquake. This method is used to obtain system descriptions in closed algebraic form with appropriate constants. The number of constants provides the designer with the minimum number of complex time-history analyses (or tests) required to characterize the systems completely. Once these constants are evaluated, parametric and optimization studies can be performed very quickly by hand. Predictions based on application of the method are made. Comparison of these predictions to results obtained from time-history solutions show the method is a valuable design tool. Application of the method to other systems is briefly discussed. 6 figures, 4 tables.
Date: January 1, 1979
Creator: Frick, T.M.
Partner: UNT Libraries Government Documents Department

Radioactive corrosion product release potential in sodium-cooled reactors

Description: A mathematical analysis of the rate of release and deposition of radioactive corrosion products from the core of liquid sodium cooled reactors is outlined and numerical results presented as a function of reactor design parameters for a number of reactors. It is shown that the activity release potential of advanced sodium-cooled reactors (FFTF and CRBRP) is about two orders of magnitude larger than that of older reactors such as EBR-II, and RAPSODIE. Radiation levels up to 6 R/hr are predicted for FFTF and CRBRP primary system components after 20 years of operation. The model can be used to predict the sensitivity of activated corrosion product release to changes in operating parameters for various existing and planned reactors.
Date: September 1, 1979
Creator: Colburn, R.P. & Taylor, G.R.
Partner: UNT Libraries Government Documents Department

Fusion-breeder-reactor design studies

Description: Studies of the technical and economic feasibility of producing fissile fuel in tandem mirrors and in tokamaks for use in fission reactors are presented. Fission-suppressed fusion breeders promise unusually good safety features and can provide make-up fuel for 11 to 18 LWRs of equal nuclear power depending on the fuel cycle. The increased revenues from sales of both electricity and fissile material might allow the commercial application of fusion technology significantly earlier than would be possible with electricity production from fusion alone. Fast-fission designs might allow a fusion reactor with a smaller fusion power and lower Q value to be economical and thus make this application of fusion even earlier. A demonstration reactor with a fusion power of 400 MW could produce 600 kg of fissile material per year at a capacity factor of 50%. The critical issues, for which small scale experiments are either being carried out or planned, are: (1) material compatibility, (2) beryllium feasibility, (3) MHD effects, and (4) pyrochemical reprocessing.
Date: April 5, 1983
Creator: Moir, R.W.; Lee, J.D. & Coops, M.S.
Partner: UNT Libraries Government Documents Department