Search results for: Kmetyk, L. N.
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1
Summary of MELCOR 1.8.2 calculations for three LOCA sequences (AG, S2D, and S3D) at the Surry plant
Authors: Kmetyk, L. N.
Published: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O [distributor], 1994Physical Description: xi, 186 pages : illustrations ; 28 cmHoldings: Loading…
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2
TRAC-PF1/MOD1 independent assessment : LOB1 large break transient A1-04R
Authors: Kmetyk, L. N.
Published: U.S. Nuclear Regulatory Commission, 1985Physical Description: x, 127 pages : illustrations ; 28 cmHoldings: Loading…
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3
RELAP5 assessment : FLECHT SEASET steam generator test 23402
Authors: Kmetyk, L. N.
Published: The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; National Technical Information Service, 1983Physical Description: viii, 58 pages : illustrations ; 28 cmHoldings: Loading…
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4
RELAP5 assessment : conclusions and user guidelines
Authors: Kmetyk, L. N.
Published: Reactor Systems Research Branch, Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Available from National Technical Information Service, 1984Physical Description: xiv, 167 pages : illustrations ; 28 cmHoldings: Loading…
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5
RELAP5 assessment : quantitative key parameters and run time statistics
Authors: Kmetyk, L. N.
Published: Reactor Systems Research Branch, Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Available from National Technical Information Service, 1984Physical Description: viii, 21 pages : illustrations ; 28 cmHoldings: Loading…
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6
Analyses of 1/15 scale Creare bypass transient experiments
Authors: Kmetyk, L. N.
Published: The Commission, 1982Physical Description: vii, 52 pages : illustrations ; 28 cmHoldings: Loading…
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7
TRAC-PF1/MOD1 independent assessment : LOB1 intermediate break test B-RIM
Authors: Kmetyk, L. N.
Published: Reactor Systems Research Branch, Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Available from Supt. of Docs., U.S. G.P.O. ; National Technical Information Service, 1986Physical Description: x, 85 pages : illustrations ; 28 cmHoldings: Loading…
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8
RELAP5 assessment : LOFT turbine trip L6-7/L9-2
Authors: Thompson, Samuel L.Other Authors: “…Kmetyk, L. N.…”
Published: The Branch : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Available from National Technical Information Service, 1983
Physical Description: xii, 98 pages : illustrations ; 28 cmHoldings: Loading…
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9
RELAP5 assessment : semiscale natural circulation tests S-NC-2 and S-NC-7
Authors: McGlaun, J. MichaelOther Authors: “…Kmetyk, L. N.…”
Published: The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Available from National Technical Information Service, 1983
Physical Description: xii, 90 pages : illustrations ; 28 cm + 1 microfiche (11 x 15 cm)Holdings: Loading…
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10
RELAP5 assessment : LOFT intermediate breaks L5-1 and L8-2
Authors: Orman, J. L. (John L.)Other Authors: “…Kmetyk, L. N.…”
Published: The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Available from National Technical Information Service, 1983
Physical Description: x, 103 pages : illustrations ; 28 cm + 1 microfiche 11 x 15 cmHoldings: Loading…
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Related Subjects
Light water reactors
Data processing
LOFT (Nuclear reactor safety test facility)
Safety measures
Accidents
Experiments
Thermodynamics
Computer programs
Fluid dynamics
Nuclear reactor accidents
Pressurized water reactors
Transients (Dynamics)
Emergency core cooling systems
Evaluation
Flow visualization
Fluid dynamic measurements
Hydraulics
Loss of coolant
Nuclear power plants
Nuclear reactors
Steam-boilers