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1
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0043040058
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Experiments to investigate the effects of fuel/coolant interactions on direct containment heating - The IET-8A and IET-8B experiments
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Sandia National Laboratories, Albuquerque, NM
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M.D. Allen, T.K. Blanchat, M. Pilch and R.T. Nichols, Experiments to investigate the effects of fuel/coolant interactions on direct containment heating - the IET-8A and IET-8B experiments, Rep. SAND92-2849, 1993 (Sandia National Laboratories, Albuquerque, NM).
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Rep. SAND92-2849
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Allen, M.D.1
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2
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0042539290
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Experiments to investigate direct containment heating phenomena with scaled models of the Zion nuclear power plant in the surtsey test facility
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May (Sandia National Laboratories, Albuquerque, NM)
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M.D. Allen et al., Experiments to investigate direct containment heating phenomena with scaled models of the Zion nuclear power plant in the Surtsey test facility, Rep. NUREG/CR-6044, SAND93-1049, May 1994 (Sandia National Laboratories, Albuquerque, NM).
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Rep. NUREG/CR-6044, SAND93-1049
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Allen, M.D.1
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3
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0010703932
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Analyses of natural circulation during a surry station blackout using SCDAP/RELAPS
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October (EG&G Idaho, Inc., Idaho Falls, ID)
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P.D. Bayless, Analyses of natural circulation during a Surry station blackout using SCDAP/RELAPS, Rep. NUREG/CR-5214, EGG-2547, October 1988 (EG&G Idaho, Inc., Idaho Falls, ID).
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Bayless, P.D.1
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0042539290
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Experiments to investigate direct containment heating phenomena with scaled models of the surry nuclear power plant
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April (Sandia National Laboratories, Albuquerque, NM)
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T.K. Blanchat et al., Experiments to investigate direct containment heating phenomena with scaled models of the Surry nuclear power plant, Rep. NUREG/CR-6152, SAND93-2519, April 1994 (Sandia National Laboratories, Albuquerque, NM).
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Rep. NUREG/CR-6152, SAND93-2519
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Blanchat, T.K.1
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5
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0041537222
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A mechanistic-specific analysis of the Zion containment overpressure fragility
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June (Sandia National Laboratories, Albuquerque, NM)
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M.P. Bohn et al., A mechanistic-specific analysis of the Zion containment overpressure fragility, Draft Rep. SAND93-1346, June 1993 (Sandia National Laboratories, Albuquerque, NM).
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(1993)
Draft Rep. SAND93-1346
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Bohn, M.P.1
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6
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0041537204
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SCDAP/RELAP5 independent peer review
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January (Los Alamos National Laboratory, Los Alamos, NM)
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M.L. Corradini et al., SCDAP/RELAP5 independent peer review, Rep. LA-1248, January 1993 (Los Alamos National Laboratory, Los Alamos, NM).
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(1993)
Rep. LA-1248
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Corradini, M.L.1
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7
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0043040067
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Analytical prediction of core heatup/liquefaction/slumping
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Cambridge, MA, August 28-September 1
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V.E. Denny and B.R. Sehgal, Analytical prediction of core heatup/liquefaction/slumping, Proc. Int. Meet. on Light Water Reactor Severe Accident Evaluation, Cambridge, MA, August 28-September 1, 1983.
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Proc. Int. Meet. on Light Water Reactor Severe Accident Evaluation
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Denny, V.E.1
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8
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0042539274
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Core to surge line energy transport in a severe accident scenario, American nuclear society
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1993 National Heat Transfer Conf., Thermal Hydraulics Division, Atlanta, GA, August 8-11
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M. di Marzo and K. Almenas, Core to surge line energy transport in a severe accident scenario, American Nuclear Society, 1993 National Heat Transfer Conf., Thermal Hydraulics Division, Atlanta, GA, August 8-11, 1993, ANS Proc. Vol. 7, pp. 339-341.
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ANS Proc.
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Di Marzo, M.1
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9
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0026170957
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Lower head creep rupture sensitivity studies
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S.S. Dosanjh and M. Pilch, Lower head creep rupture sensitivity studies, Nucl. Sci. Eng., 108 (1991) 172.
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Nucl. Sci. Eng.
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Dosanjh, S.S.1
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10
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The three mile island unit 2 core relocation - Heat transfer mechanisms
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M. Epstein and H.K. Fauske, The Three Mile Island unit 2 core relocation - heat transfer mechanisms, Nucl. Technol., 87 (1989) 1021.
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12
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48549083231
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Depressurization as an accident management strategy to minimize the consequence of DCH
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October (US Nuclear Regulatory Commission, Washington, DC)
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D.J. Hanson et al., Depressurization as an accident management strategy to minimize the consequence of DCH, Rep. NUREG/CR-5447, October 1990 (US Nuclear Regulatory Commission, Washington, DC).
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Rep. NUREG/CR-5447
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Hanson, D.J.1
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13
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0042539278
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Integrated MELPROG/TRAC analyses of a PWR station blackout
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T.J. Heames and R.C. Smith, Integrated MELPROG/TRAC analyses of a PWR station blackout, Nucl. Eng. Des., 125 (1991) 175.
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Heames, T.J.1
Smith, R.C.2
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14
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0041537208
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Separate effects experiments on phenomena of direct containment heating - Air-water simulation experiments in Zion geometry
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Q. W, March (Purdue University, West Lafayette, IN)
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M. Ishii, S.T. Revankar, G. Zhang, Q. W, and P. O'Brien, Separate effects experiments on phenomena of direct containment heating - air-water simulation experiments in Zion geometry, Rep. PU NE-93/1, March 1993 (Purdue University, West Lafayette, IN).
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Rep. PU NE-93/1
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Ishii, M.1
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Zhang, G.3
O'Brien, P.4
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15
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0042038444
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MELPROG-PWT/MODI analysis of a TMLB′ accident sequence
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January (Sandia National Laboratories, Albuquerque, NM)
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J.E. Kelly, R.J. Henninger and J.F. Dearing, MELPROG-PWT/MODI analysis of a TMLB′ accident sequence, Rep. NUREG/CR-4742, SAND86-2175, January 1987 (Sandia National Laboratories, Albuquerque, NM).
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Kelly, J.E.1
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Dearing, J.F.3
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17
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0043040070
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Assessment of the potential for high pressure melt ejection resulting from a surry station blackout transient
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November (EG&G Idaho, Inc., Idaho Falls, ID)
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D.L. Knudson and C.A. Dobbe, Assessment of the potential for high pressure melt ejection resulting from a Surry station blackout transient, Rep. NUREG/CR-5949, EGG-2689, November 1993b (EG&G Idaho, Inc., Idaho Falls, ID).
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Knudson, D.L.1
Dobbe, C.A.2
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18
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65549166195
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Independent review of SCDAP/RELAP5 natural circulation calculations
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August (Sandia National Laboratories, Albuquerque, NM)
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G.M. Martinez, R.J. Gross, M.J. Martinez and G.S. Rightly, Independent review of SCDAP/RELAP5 natural circulation calculations, Rep. SAND91-2089, August 1992 (Sandia National Laboratories, Albuquerque, NM).
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Rep. SAND91-2089
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Martinez, G.M.1
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Martinez, M.J.3
Rightly, G.S.4
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20
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0042038445
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Rep. NUREG-1365, Rev. 1, December (US Nuclear Regulatory Commission, Washington, DC)
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NRC, Severe accident research program plan update, Rep. NUREG-1365, Rev. 1, December 1992 (US Nuclear Regulatory Commission, Washington, DC).
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Severe Accident Research Program Plan Update
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21
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0043040069
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High pressure ejection of melt from a reactor pressure vessel: The discharge phase
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September (Sandia National Laboratories, Albuquerque, NM)
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M. Pilch and W.W. Tarbell, High pressure ejection of melt from a reactor pressure vessel: the discharge phase, Rep. NUREG/CR-4383, SAND85-0012, September 1985 (Sandia National Laboratories, Albuquerque, NM).
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Rep. NUREG/CR-4383, SAND85-0012
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Pilch, M.1
Tarbell, W.W.2
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22
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0041537221
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Preliminary calculations on direct heating of a containment atmosphere by airborne core debris
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July (Sandia National Laboratories, Albuquerque, NM)
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M. Pilch and W.W. Tarbell, Preliminary calculations on direct heating of a containment atmosphere by airborne core debris, Rep. NUREG/CR-4455, SAND85-2439, July 1986 (Sandia National Laboratories, Albuquerque, NM).
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Rep. NUREG/CR-4455, SAND85-2439
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Pilch, M.1
Tarbell, W.W.2
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23
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0043040057
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Letter Rep. to the NRC, (Sandia National Laboratories, Albuquerque, NM)
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M.M. Pilch, M.D. Allen and J.L. Binder, Counterpart and replicate DCH experiments conducted at two different physical scales: the SNL/IET-1, 1R and the ANL/IET-1R, 1RR experiments, Letter Rep. to the NRC, 1992 (Sandia National Laboratories, Albuquerque, NM).
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(1992)
Counterpart and Replicate DCH Experiments Conducted at Two Different Physical Scales: the SNL/IET-1, 1R and the ANL/IET-1R, 1RR Experiments
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Pilch, M.M.1
Allen, M.D.2
Binder, J.L.3
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24
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0008649386
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December (Sandia National Laboratories, Albuquerque, NM)
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M.M. Pilch, H. Yan and T.G. Theofanous, The probability of containment failure by direct containment heating in Zion, Rep. NUREG/CR-6075, SAND93-1535, December 1994 (Sandia National Laboratories, Albuquerque, NM).
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The Probability of Containment Failure by Direct Containment Heating in Zion, Rep. NUREG/CR-6075, SAND93-1535
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Pilch, M.M.1
Yan, H.2
Theofanous, T.G.3
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25
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0042539281
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Reactor coolant pump shaft seal stability during station blackout
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May (EG&G Idaho, Inc., Idaho Falls, ID)
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D.B. Rhodes, R.C. Hill and R.G. Wensel, Reactor coolant pump shaft seal stability during station blackout, Rep. NUREG/CR-4821, EG&G-2492, AECL-9342, May 1987 (EG&G Idaho, Inc., Idaho Falls, ID).
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Rep. NUREG/CR-4821, EG&G-2492, AECL-9342
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Rhodes, D.B.1
Hill, R.C.2
Wensel, R.G.3
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26
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0041537202
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Late phase melt progression scoping and sensitivity studies, draft
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Sandia National Laboratories, Albuquerque, NM
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R.L. Schmidt and L.L. Humphries, Late phase melt progression scoping and sensitivity studies, Draft, Rep. SAND92-2831, 1993 (Sandia National Laboratories, Albuquerque, NM).
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Rep. SAND92-2831
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Schmidt, R.L.1
Humphries, L.L.2
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28
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0003836434
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August (US Nuclear Regulatory Commission, Washington, DC)
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T.G. Theofanous, W.H. Amarasooriya, H. Yan and U. Ratnam, The probability of liner failure in mark-I containment, Rep. NUREG/CR-5423, August 1991 (US Nuclear Regulatory Commission, Washington, DC).
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The Probability of Liner Failure in Mark-I Containment, Rep. NUREG/CR-5423
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Theofanous, T.G.1
Amarasooriya, W.H.2
Yan, H.3
Ratnam, U.4
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29
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0041537207
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The probability of mark-I containment failure by melt attack on the liner
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November
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T.G. Theofanous et al., The probability of mark-I containment failure by melt attack on the liner, Rep. NUREG/ CR-6025, November 1993.
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Rep. NUREG/ CR-6025
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Theofanous, T.G.1
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30
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0041537203
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Low pressure cutoff for melt dispersal from reactor cavities
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Washington DC, 30 October to 4 November
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N.K. Tutu, T. Ginsberg and L. Fintrok, Low pressure cutoff for melt dispersal from reactor cavities, Fourth Proc. of Nuclear Thermal Hydraulics, ANS/ENS Int. Conf., Washington DC, 30 October to 4 November, 1988, pp. 29-37.
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Fourth Proc. of Nuclear Thermal Hydraulics, ANS/ENS Int. Conf.
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Tutu, N.K.1
Ginsberg, T.2
Fintrok, L.3
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31
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0043040059
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Estimation of containment pressure loading due to direct containment heating for the Zion plant
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January (Brookhaven National Laboratory, Upton, NY)
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N.K. Tutu, C.K. Park, C.A. Grimshaw and T. Ginsberg, Estimation of containment pressure loading due to direct containment heating for the Zion plant, Rep. NUREG/ CR-5282, BNL-NUREG-52181, January 1990 (Brookhaven National Laboratory, Upton, NY).
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Rep. NUREG/ CR-5282, BNL-NUREG-52181
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Tutu, N.K.1
Park, C.K.2
Grimshaw, C.A.3
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32
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0028463730
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Local creep rupture failure modes on a corium-loaded lower head
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in Press
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R.J. Witt, Local creep rupture failure modes on a corium-loaded lower head, in Press, Nucl. Eng. Des., 148 (1994) 385.
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Witt, R.J.1
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0003586883
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An integrated structure and scaling methodology for severe accident technical issue resolution
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EG&G Idaho, Inc., Idaho Falls, ID
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N. Zuber et al., An integrated structure and scaling methodology for severe accident technical issue resolution, Rep. NUREG/CR-5809, EGG-2659, 1991 (EG&G Idaho, Inc., Idaho Falls, ID).
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Rep. NUREG/CR-5809, EGG-2659
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Zuber, N.1
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