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LMFBR safety testing needs and the conceptual design of a new safety research experiment facility

Description: Experiment needs for the LMFBR safety program are reviewed. The screening of reactor concepts which would meet the needs is described and a conceptual design for a new safety research experiment facility is presented. (JWR)
Date: September 1, 1975
Creator: Marchaterre, J.F.; Matlock, R.G. & Goldman, A.J.
Partner: UNT Libraries Government Documents Department

Implicit Eulerian method for analyzing transient phenomena in fast reactors

Description: An Eulerian compressible hydrodynamic method is presented for analyzing transient phenomena in nuclear reactors following hypothetical excursions. The method uses the implicit integration scheme to solve nonlinear equations of fluid dynamics in conjunction with a thin-shell analysis to calculate the response of the wall boundary. Detailed formulations are given. Results are presented for two example problems and compared with available experimental data. 6 references. (auth)
Date: October 1, 1975
Creator: Wang, C.Y.
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

Hypothetical core disruptive accident

Description: The hypothetical core disruptive accident in an LMFBR is discussed under the following main headings: reactor dynamics; mechanical consequences; and post- accident heat removal. 79 references. (DCC)
Date: July 1, 1975
Creator: Simpson, D.E.
Partner: UNT Libraries Government Documents Department

Summary and evaluation: fuel dynamics loss-of-flow experiments (tests L2, L3, and L4)

Description: Three similar experiments conducted to support the analyses of hypothetical LMFBR unprotected-loss-of-flow accidents are summarized and evaluated. The tests, designated L2, L3, and L4, provided experimental data against which accident-analysis codes could be compared, so as to guide further analysis and modeling of the initiating phases of the hypothetical accident. The tests were conducted using seven-pin bundles of mixed-oxide fuel pins in Mark-II flowing-sodium loops in the TREAT reactor. Test L2 used fresh fuel. Tests L3 and L4 used irradiated fuel pins having, respectively, ''intermediate-power'' (no central void) and ''high-power'' (fully developed central void) microstructure. 12 references. (auth)
Date: September 1, 1975
Creator: Barts, E.W.; Deitrich, L.W.; Eberhart, J.G.; Fischer, A.K. & Meek, C.C.
Partner: UNT Libraries Government Documents Department

Annual technical progress report nuclear safety characterization of sodium fires and fast reactor fission products, government fiscal year 1975

Description: Progress is reported in the areas of sodium jet dispersal tests, stationary sodium drop tests, SOMIX code development, buoyant bubble rise tests, aerosol leakage, fuel and fission product release from burning sodium, and at- temperature properties of fuel mixture. (GD)
Date: August 15, 1975
Partner: UNT Libraries Government Documents Department

Nuclear safety characterization of sodium fires and fast reactor fission products. Quarterly technical progress report, January--March 1975

Description: Progress is reported in the areas of sodium splash dispersal, SOMIX code development, HCDA aerosol source term, aerosol leakage, fuel and fission product release from burning sodium, and high temperature properties of fuel mixtures. (JWR)
Date: May 15, 1975
Partner: UNT Libraries Government Documents Department