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1
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0038754024
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Three mile Island unit 1 main steam line break three dimensional neutronics/thermal-hydraulics analysis: Application of different coupled codes
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F. D'AURIA, J. L. GAGO MORENO, G. M. GALASSI, D. GRGIC, and A. SPADONI, "Three Mile Island Unit 1 Main Steam Line Break Three Dimensional Neutronics/Thermal-Hydraulics Analysis: Application of Different Coupled Codes," Nucl. Technol., 142, 180 (2003).
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Spadoni, A.5
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2
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84959035184
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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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San Francisco, California, July 18-23
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F. D'AURIA, G. M. GALASSI, J. L. GAGO MORENO, 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.
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D'Auria, F.1
Galassi, G.M.2
Gago Moreno, J.L.3
Cappariello, A.4
Bajs, T.5
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3
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1842594531
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Boiling water reactor turbine trip (TT) benchmark, vol. 1: Final specifications
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Nuclear Energy Agency
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J. SOLIS, K. N. IVANOV, B. SARIKAYA, A. M. OLSON, and K. W. HUNT, "Boiling Water Reactor Turbine Trip (TT) Benchmark, Vol. 1: Final Specifications," NEA/NSC/DOC, Nuclear Energy Agency (2001).
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NEA/NSC/DOC
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Solis, J.1
Ivanov, K.N.2
Sarikaya, B.3
Olson, A.M.4
Hunt, K.W.5
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4
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0038435755
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Core design and operating data for cycles 1 and 2 peach bottom 2
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Electric Power Research Institute
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N. H. LARSEN, "Core Design and Operating Data for Cycles 1 and 2 Peach Bottom 2," EPRI NP-563, Electric Power Research Institute (1978).
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EPRI NP-563
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Larsen, N.H.1
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5
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9144263308
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Self-limiting power excursion tests of a water moderated low-enrichment UO2 core in SPERT-1
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A. H. SPANO, J. E. BARRY, L. A. STEPHAN, and J. C. YOUNG, "Self-Limiting Power Excursion Tests of a Water Moderated Low-Enrichment UO2 Core in SPERT-1," IDO-16751 (1962).
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IDO-16751
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Spano, A.H.1
Barry, J.E.2
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6
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9144260281
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RELAP5/MOD3, code manual: User guide and input requirements
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EGG-2396, EG&G Idaho
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V. H. RANSOM, R. J. WAGNER, J. A. TRAPP, G. W. JOHNSEN, C. S. MILLER, D. M. KISER, and R. A. RIEMKE, "RELAP5/MOD3, Code Manual: User Guide and Input Requirements," NUREG/CR-4312 EGG-2396, EG&G Idaho (1990).
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NUREG/CR-4312
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Ransom, V.H.1
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Johnsen, G.W.4
Miller, C.S.5
Kiser, D.M.6
Riemke, R.A.7
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7
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0008577463
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PARCS: A multi-dimensional two group reactor kinetics code based on the nonlinear analytic nodal method
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H. G. JOO, D. BARBER, G. JIANG, and T. J. DOWNAR, "PARCS: A Multi-Dimensional Two Group Reactor Kinetics Code Based on the Nonlinear Analytic Nodal Method," PU/NE-98-26 (1998).
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PU/NE-98-26
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Joo, H.G.1
Barber, D.2
Jiang, G.3
Downar, T.J.4
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8
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3843072257
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Transient and stability tests at peach bottom atomic power station unit 2 at end of cycle 2
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Electric Power Research Institute
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L. A. CARMICHAEL and R. O. NIEMI, "Transient and Stability Tests at Peach Bottom Atomic Power Station Unit 2 at End of Cycle 2," EPRI NP-564, Electric Power Research Institute (1978).
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EPRI NP-564
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Carmichael, L.A.1
Niemi, R.O.2
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9
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9144226117
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Preliminary results for exercise 3 using coupled RELAPS/PARCS codes
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Rossendorf (Dresden), Germany, May 28-30
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A. BOUSBIA SALAH, J. VEDOVI, G. M. GALASSI, and F. D'AURIA, "Preliminary Results for Exercise 3 Using Coupled RELAPS/PARCS Codes," presented at 3rd Workshop OECD/NRC Boiling Water Reactor Turbine Trip Benchmark, Rossendorf (Dresden), Germany, May 28-30, 2002.
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3rd Workshop OECD/NRC Boiling Water Reactor Turbine Trip Benchmark
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Bousbia Salah, A.1
Vedovi, J.2
Galassi, G.M.3
D'Auria, F.4
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10
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1842542108
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Analysis of the peach bottom 2 BWR turbine trip experiment by RELAP5/ Mod3.2
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A. BOUSBIA SALAH and F. D'AURIA, "Analysis of the Peach Bottom 2 BWR Turbine Trip Experiment by RELAP5/ Mod3.2," Nucl. Technol. Radiat. Prot., XVII, 1/2, 44 (2002).
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Nucl. Technol. Radiat. Prot.
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Bousbia Salah, A.1
D'Auria, F.2
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11
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9144266028
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Analysis of self-shutdown behavior in the SPERT I reactor
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S. G. FORBES, F. L. BENTZEN, P. FRENCH, J. E. GRUND, J. C. HAIRE, W. E. NYER, and R. F. WALKER, "Analysis of Self-Shutdown Behavior in the SPERT I Reactor," IDO-16528 (1958).
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IDO-16528
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Forbes, S.G.1
Bentzen, F.L.2
French, P.3
Grund, J.E.4
Haire, J.C.5
Nyer, W.E.6
Walker, R.F.7
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12
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9144233227
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Reactor excursion behavior
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Geneva, Switzerland
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W. E. NYER, G. O. BRIGHT, and R. J. McWHORTER, "Reactor Excursion Behavior," Proc. 3rd UN Int. Conf. Peacefill Uses of Atomic Energy, Geneva, Switzerland, Vol. 13, p. 13 (1965).
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Nyer, W.E.1
Bright, G.O.2
McWhorter, R.J.3
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14
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9144265181
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Cross section derivation
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UPC Barcelona, Spain, January 23-24
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K. N. IVANOV et al., "Cross Section Derivation," presented at 3rd Crissue-s Mtg., UPC Barcelona, Spain, January 23-24, 2003.
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3rd Crissue-s Mtg.
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Ivanov, K.N.1
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15
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0031997275
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More than 30 years of reactor thermal hydraulics
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F. D'AURIA and A. B. WAHBA, "More than 30 Years of Reactor Thermal Hydraulics," Kerntech., 63, 1/2, 8 (1998).
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Kerntech.
, vol.63
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D'Auria, F.1
Wahba, A.B.2
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16
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0031621864
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Code validation and uncertainties in system thermal-hydraulics
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F. D'AURIA and G. M. GALASSI, "Code Validation and Uncertainties in System Thermal-Hydraulics," Prog. Nucl. Energy, 33, 1/2, 175 (1998).
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Prog. Nucl. Energy
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D'Auria, F.1
Galassi, G.M.2
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17
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84885254022
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Peach bottom turbine trip benchmark analysis with RELAP5-3D coupled code
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West Yellowstone, Montana, August 27-29
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A. SPADONI, A. BOUSBIA SALAH, F. D'AURIA, G. GALASSI, and J. VEDOVI, "Peach Bottom Turbine Trip Benchmark Analysis with RELAP5-3D Coupled Code," 2003 Relap5 International Users Seminar, West Yellowstone, Montana, August 27-29, 2003.
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(2003)
2003 Relap5 International Users Seminar
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Spadoni, A.1
Bousbia Salah, A.2
D'Auria, F.3
Galassi, G.4
Vedovi, J.5
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18
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9144223385
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Experimental study of transient behavior in a subcooled, water moderated reactor
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F. SCHROEDER, S. G. FORBES, W. E. NYER, F. L. BENTZEN, and G. O. BRIGHT, "Experimental Study of Transient Behavior in a Subcooled, Water Moderated Reactor," Nucl. Sci. Eng., 2, 96 (1957).
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Nucl. Sci. Eng.
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Bright, G.O.5
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19
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0017728327
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The significance of fast moderator feedback effects in a boiling water reactor during severe pressure transients
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W. FRISCH, S. LANGENBUCH, and P. PETERNELL, "The Significance of Fast Moderator Feedback Effects in a Boiling Water Reactor During Severe Pressure Transients," Nucl. Sci. Eng., 64, 843 (1977).
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Frisch, W.1
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