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1
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0031621864
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Code validation and uncertainties in system thermalhydraulics
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F. D'Auria and G. M. Galassi, "Code Validation and Uncertainties in System Thermalhydraulics," Proc. Nucl. Energy, 33, 1/2, 175 (1998).
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(1998)
Proc. Nucl. Energy
, vol.33
, Issue.1-2
, pp. 175
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D'Auria, F.1
Galassi, G.M.2
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2
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0037760847
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A methodology for the qualification of thermalhydraulic codes nodalizations
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M. Bonuccelli, F. D'Auria, N. Debrecin, and G. M. Galassi, "A Methodology for the Qualification of Thermalhydraulic Codes Nodalizations," presented at 6th Int. Topl. Mtg. Nuclear Reactor Thermalhydraulics, Grenoble, France, October 5-8, 1993.
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6th Int. Topl. Mtg. Nuclear Reactor Thermalhydraulics, Grenoble, France, October 5-8, 1993
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Bonuccelli, M.1
D'Auria, F.2
Debrecin, N.3
Galassi, G.M.4
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3
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0029172648
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Outline of the uncertainty methodology based on accuracy extrapolation
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F. D'Auria, N. Debrecin, and G. M. Galassi, "Outline of the uncertainty methodology based on accuracy extrapolation," Nucl. Technol., 109, 21 (1995).
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(1995)
Nucl. Technol.
, vol.109
, pp. 21
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D'Auria, F.1
Debrecin, N.2
Galassi, G.M.3
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4
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0031245970
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Determination of code accuracy in predicting small break LOCA experiment
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B. Mavko, A. Prosek, and F. D'Auria, "Determination of Code Accuracy in Predicting Small Break LOCA Experiment," Nucl. Technol., 120, 1 (1997).
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(1997)
Nucl. Technol.
, vol.120
, pp. 1
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Mavko, B.1
Prosek, A.2
D'Auria, F.3
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5
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0031997275
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More than 30 years of reactor thermalhydraulics
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F. D'Auria and A. B. Wahba, "More Than 30 Years of Reactor Thermalhydraulics," J. Kerntechnik, 63, 1-2, 8 (1998).
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(1998)
J. Kerntechnik
, vol.63
, Issue.1-2
, pp. 8
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D'Auria, F.1
Wahba, A.B.2
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6
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0003466140
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PWR main steam line break (MSLB) benchmark - Volume I: Final specifications
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NEA/NSC/DOC(99)8-Paris (F), Nuclear Energy Agency (Apr.)
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K. I. Ivanov, T. M. Beam, A. J. Baratta, A. Irani, and N. Trikouros, "PWR Main Steam Line Break (MSLB) Benchmark - Volume I: Final Specifications," NEA/NSC/DOC(99)8-Paris (F), Nuclear Energy Agency (Apr. 1999).
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(1999)
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Ivanov, K.I.1
Beam, T.M.2
Baratta, A.J.3
Irani, A.4
Trikouros, N.5
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7
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0037760843
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Participation in the OECD/NEA/NSC TMI-1 MSLB benchmark - Phase 1 0-D neutronics
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DCMN-NT 328(98), Pisa (I), University of Pisa (Jan.)
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A. Cappariello, F. D'Auria, G. M. Galassi, and T. Bajs, "Participation in the OECD/NEA/NSC TMI-1 MSLB Benchmark - Phase 1 0-D Neutronics," DCMN-NT 328(98), Pisa (I), University of Pisa (Jan. 1998).
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(1998)
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Cappariello, A.1
D'Auria, F.2
Galassi, G.M.3
Bajs, T.4
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8
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0037760843
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Participation in the OECD/NEA/NSC TMI-1 PWR MSLB benchmark. Phase 1: 0-D neutronics.-Final results
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DCMN-NT 328(98), Pisa (I), University of Pisa (Mar.)
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A. Cappariello, F. D'Auria, G. M. Galassi, and T. Bajs, "Participation in the OECD/NEA/NSC TMI-1 PWR MSLB Benchmark. Phase 1: 0-D Neutronics.-Final Results," DCMN-NT 328(98), Pisa (I), University of Pisa (Mar. 1998).
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(1998)
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Cappariello, A.1
D'Auria, F.2
Galassi, G.M.3
Bajs, T.4
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9
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4243796667
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Aspetti tridimensionali relativi alla sicurezza degli impianti nucleari
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Thesis in nuclear engineering, University of Pisa
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A. Cappariello, "Aspetti tridimensionali relativi alla sicurezza degli impianti nucleari," Thesis in nuclear engineering, University of Pisa (1996/97).
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(1996)
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Cappariello, A.1
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10
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0037760848
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Application of relap5/mod3.2 to the OECD/CSNI/NSC main steam line break benchmark related to TMI-1
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F. D'Auria, G. M. Galassi, J. L. Gago, A. Cappariello, and T. Bajs, "Application of Relap5/mod3.2 to the OECD/CSNI/NSC Main Steam Line Break Benchmark Related to TMI-1," presented at 3rd ASME/JSME Joint Fluid Engineering Conf., San Francisco, California, July 18-23, 1999.
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3rd ASME/JSME Joint Fluid Engineering Conf., San Francisco, California, July 18-23, 1999
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D'Auria, F.1
Galassi, G.M.2
Gago, J.L.3
Cappariello, A.4
Bajs, T.5
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11
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0038437395
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Achievements from the analysis of a main steam line break in a PWR
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F. D'Auria, J. L. Gago, G. Galassi, "Achievements from the Analysis of a Main Steam Line Break in a PWR," presented at 25th Reunion Annual Sociedad Nuclear Espanola, Granada, Spain, November 17-19, 1999.
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25th Reunion Annual Sociedad Nuclear Espanola, Granada, Spain, November 17-19, 1999
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D'Auria, F.1
Gago, J.L.2
Galassi, G.3
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12
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0038098355
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Derivation of cross section library for 3-D neutronics calculation with Parcs Code
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DCMN NT 386(99), Pisa (I), University of Pisa (Oct.)
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J. L. Gago, "Derivation of Cross Section Library for 3-D Neutronics Calculation with Parcs Code," DCMN NT 386(99), Pisa (I), University of Pisa (Oct. 1999).
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(1999)
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Gago, J.L.1
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13
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0037760845
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Preliminary report on first phase of OECD PWR MSLB benchmark
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T. M. Beam, K. N. Ivanov, and A. J. Baratta, "Preliminary Report on First Phase of OECD PWR MSLB Benchmark," presented at 2nd Benchmark Workshop, Madrid, Spain, May 22-23, 1998.
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2nd Benchmark Workshop, Madrid, Spain, May 22-23, 1998
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Beam, T.M.1
Ivanov, K.N.2
Baratta, A.J.3
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14
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0038775224
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TMI-1 MSLB coupled 3-D neutronics/thermalhydraulics analysis: Planning and results
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DCMN NT 398(00)-Rev.1, Pisa (I), University of Pisa (Feb.)
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F. D'Auria, J. L. Gago, and G. M. Galassi, "TMI-1 MSLB Coupled 3-D Neutronics/Thermalhydraulics Analysis: Planning and Results," DCMN NT 398(00)-Rev.1, Pisa (I), University of Pisa (Feb. 2000).
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(2000)
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D'Auria, F.1
Gago, J.L.2
Galassi, G.M.3
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15
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0038437386
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RELAP5/MOD3.2 code manual
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NUREG/CR-5535, INEL-95/0174, U.S. Nuclear Regulatory Commission (Aug.)
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"RELAP5/MOD3.2 Code Manual," NUREG/CR-5535, INEL-95/0174, U.S. Nuclear Regulatory Commission (Aug. 1995)
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(1995)
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16
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1842551896
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RELAP5-3D code manual
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The Relap5-3D Team; INEEL-EXT-98-0083-Rev. 1.2, Idaho National Engineering and Environmental Laboratory (May)
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The Relap5-3D Team, "RELAP5-3D Code Manual," INEEL-EXT-98-0083-Rev. 1.2, Idaho National Engineering and Environmental Laboratory (May 2000).
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(2000)
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17
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0003599718
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Cobra/TRAC: A thermalhydraulic code for transient analysis of nuclear reactor vessel and primary coolant system
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NUREG/CR 2046, PNL 4385, Pacific Northwest Laboratory (Mar.)
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M. Thurgood et al., "Cobra/TRAC: A Thermalhydraulic Code for Transient Analysis of Nuclear Reactor Vessel and Primary Coolant System," NUREG/CR 2046, PNL 4385, Pacific Northwest Laboratory (Mar. 1983).
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(1983)
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Thurgood, M.1
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18
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0038437393
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QUABBOX/CUBBOX-HYCA, Ein Dreidimensionales Kernmodell mit parallelen Kuhlkanalen fur Leichtwasserreaktoren
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GRS-A-926, Garching (G), Gesellschaft für Anlage- und Reaktorsicherheit
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S. Langenbuch, "QUABBOX/CUBBOX-HYCA, Ein Dreidimensionales Kernmodell mit parallelen Kuhlkanalen fur Leichtwasserreaktoren," GRS-A-926, Garching (G), Gesellschaft für Anlage- und Reaktorsicherheit (1984).
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(1984)
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Langenbuch, S.1
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19
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0003765311
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PARCS: A multidimensional two-group reactor kinetic code based on the nonlinear analytical nodal method
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PU/NE-98-26, Purdue University
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H. G. Joo, D. A. Barber, G. Jiang, and T. J. Downar, "PARCS: A Multidimensional Two-Group Reactor Kinetic Code Based on the Nonlinear Analytical Nodal Method," PU/NE-98-26, Purdue University (1998).
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(1998)
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Joo, H.G.1
Barber, D.A.2
Jiang, G.3
Downar, T.J.4
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20
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0038098358
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Final completion report for the coupled relap5/parcs code
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PU/NE-98-31, Purdue University
-
D. A. Barber, T. J. Downar, and W. Wang, "Final Completion Report for the Coupled Relap5/Parcs Code," PU/NE-98-31, Purdue University (1998).
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(1998)
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Barber, D.A.1
Downar, T.J.2
Wang, W.3
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21
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0011127009
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NESTLE: A few-group neutron diffusion equation solver utilizing the nodal expansion method for eigenvalue, adjoint, fixed-source steady state and transient problems
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EGG-NRE-11406, Idaho National Engineering Laboratory (June)
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P. J. Turinsky et al., "NESTLE: A Few-Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method for Eigenvalue, Adjoint, Fixed-Source Steady State and Transient Problems," EGG-NRE-11406, Idaho National Engineering Laboratory (June 1994).
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(1994)
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Turinsky, P.J.1
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