-
1
-
-
14544292682
-
Report of the uncertainty method study for advanced best estimate thermal hydraulic code applications
-
OECD/CSNI (June)
-
T. WICKETT et al., "Report of the Uncertainty Method Study for Advanced Best Estimate Thermal Hydraulic Code Applications," NEA/CSNI R (97) 35, Vols. I and II, OECD/CSNI (June 1998).
-
(1998)
NEA/CSNI R (97) 35
, vol.1-2
-
-
Wickett, T.1
-
2
-
-
11144237000
-
An overview of the code scaling, applicability and uncertainty evaluation methodology
-
B. E. BOYACK, I. CATTON, R. B. DUFFEY, P. GRIFFITH, K. R. KATSMA, G. S. LELLOUCHE, S. LEVY, U. S. ROHATGI, G. E. WILSON, W. WULFF, and N. ZUBER, "An Overview of the Code Scaling, Applicability and Uncertainty Evaluation Methodology," Nucl. Eng. Design, 119, 1, I (1990).
-
(1990)
Nucl. Eng. Design
, vol.119
, Issue.1
-
-
Boyack, B.E.1
Catton, I.2
Duffey, R.B.3
Griffith, P.4
Katsma, K.R.5
Lellouche, G.S.6
Levy, S.7
Rohatgi, U.S.8
Wilson, G.E.9
Wulff, W.10
Zuber, N.11
-
4
-
-
0029172648
-
Outline of the uncertainty methodology based on accuracy extrapolation
-
F. D'AURIA, N. DEBRECIN, and G. M. GALASSI, "Outline of the Uncertainty Methodology Based on Accuracy Extrapolation," J. Nucl. Technol., 109, 1, 21 (1995).
-
(1995)
J. Nucl. Technol.
, vol.109
, Issue.1
, pp. 21
-
-
D'Auria, F.1
Debrecin, N.2
Galassi, G.M.3
-
5
-
-
0342895096
-
RELAP5/MOD3 code manual, vol. I: Code structure, system models, and solution methods
-
C. M. ALLISON, C. S. MILLER, and N. L. WADE, Eds., U.S. NRC, Washington, D.C. (June)
-
K. E. CARLSON, R. A. RIEMKE, S. Z. ROUHANIG, R. W. SHUMWAY, and W. L. WEAVER, "RELAP5/MOD3 Code Manual, Vol. I: Code Structure, System Models, and Solution Methods," NUREG/CR-5535, C. M. ALLISON, C. S. MILLER, and N. L. WADE, Eds., U.S. NRC, Washington, D.C. (June 1990).
-
(1990)
NUREG/CR-5535
-
-
Carlson, K.E.1
Riemke, R.A.2
Rouhanig, S.Z.3
Shumway, R.W.4
Weaver, W.L.5
-
6
-
-
0003765311
-
-
PU/NE-98-26, Purdue University
-
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, Purdue University (1998).
-
(1998)
PARCS: A Multi-dimensional Two Group Reactor Kinetics Code Based on the Nonlinear Analytic Nodal Method
-
-
Joo, H.G.1
Barber, D.2
Jiang, G.3
Downar, T.J.4
-
7
-
-
0343345560
-
Application of RELAP5/MOD3 to the evaluation of loss of feedwater in test facilities and in nuclear plants
-
F. D'AURIA, N. DEBRECIN, G. M. GALASSI, and S. GALEAZZI, "Application of RELAP5/MOD3 to the Evaluation of Loss of Feedwater in Test Facilities and in Nuclear Plants," Nucl. Eng. Design, 141, 3 (1993).
-
(1993)
Nucl. Eng. Design
, vol.141
, pp. 3
-
-
D'Auria, F.1
Debrecin, N.2
Galassi, G.M.3
Galeazzi, S.4
-
8
-
-
0042963680
-
Application of a statistical model to the evaluation of counterpart test database
-
S. BELSITO, F. D'AURIA, and G. M. GALASSI, "Application of a Statistical Model to the Evaluation of Counterpart Test Database," J. Kerntechnik, 59, 3 (1994).
-
(1994)
J. Kerntechnik
, vol.59
, pp. 3
-
-
Belsito, S.1
D'Auria, F.2
Galassi, G.M.3
-
9
-
-
0343345563
-
Description of the UMAE methodology
-
University of Pisa (Mar.)
-
F. D'AURIA and A. ERAMO, "Description of the UMAE Methodology," DCMN NT 325(98), University of Pisa (Mar. 1998).
-
(1998)
DCMN NT
, vol.325
, Issue.98
-
-
D'Auria, F.1
Eramo, A.2
-
10
-
-
0345254116
-
Thermal hydraulics of emergency core cooling in light water reactors - A state of the art report
-
M. J. LEWIS, Ed., Organisation for Economic Cooperation and Development/Committee on the Safety of Nuclear Installations (Oct.)
-
M. J. LEWIS, R. POCHARD, F. D'AURIA, H. KARWAT, K.WOLFERT, G. YADIGAROGLU, and H. L. O. HOLM-STROM, "Thermal Hydraulics of Emergency Core Cooling in Light Water Reactors - A State of the Art Report," OECD/ CSNI 161, M. J. LEWIS, Ed., Organisation for Economic Cooperation and Development/Committee on the Safety of Nuclear Installations (Oct. 1989).
-
(1989)
OECD/ CSNI
, vol.161
-
-
Lewis, M.J.1
Pochard, R.2
D'Auria, F.3
Karwat, H.4
Wolfert, K.5
Yadigaroglu, G.6
Holm-Strom, H.L.O.7
-
11
-
-
0042963684
-
A separate effects test matrix for thermal-hydraulic code validation: Phenomena characterization and selection of facilities and tests
-
Organisation for Economic Co-operation and Development/Committee on the Safety of Nuclear Installations
-
N. AKSAN, F. D'AURIA, H. GLAESER, R. POCHARD, C. RICHARDS, and A. SJOBERG, "A Separate Effects Test Matrix for Thermal-Hydraulic Code Validation: Phenomena Characterization and Selection of Facilities and Tests," OECD/GD (94) 82, Vols. I and II, Organisation for Economic Co-operation and Development/Committee on the Safety of Nuclear Installations (1993).
-
(1993)
OECD/GD (94) 82
, vol.1-2
-
-
Aksan, N.1
D'Auria, F.2
Glaeser, H.3
Pochard, R.4
Richards, C.5
Sjoberg, A.6
-
12
-
-
22344451417
-
Internal assessment of uncertainty, proposal for finalising the out-comings of uncertainty methodologies
-
rev. 1, University of Pisa (Apr.)
-
F. D'AURIA, A. ERAMO, and W. GIANNOTTI, "Internal Assessment of Uncertainty, Proposal for Finalising the Out-comings of Uncertainty Methodologies," DCMN NT 308(97) rev. 1, University of Pisa (Apr. 1997).
-
(1997)
DCMN NT
, vol.308
, Issue.97
-
-
D'Auria, F.1
Eramo, A.2
Giannotti, W.3
-
13
-
-
85039465498
-
Status approach in the analysis of complex transient in PWR systems
-
Turin, Italy, June 19-20
-
F. D'AURIA, A. ERAMO, and P. GATTA, "Status Approach in the Analysis of Complex Transient in PWR Systems," Proc. Conf. 15th UIT National Heat Transfer, Turin, Italy, June 19-20, 1997.
-
(1997)
Proc. Conf. 15th UIT National Heat Transfer
-
-
D'Auria, F.1
Eramo, A.2
Gatta, P.3
-
14
-
-
0001904923
-
The 1995 look-up tables for critical heat flux in tubes
-
D. C. GROENEVELD, L. K. H. LEUNG, P. L. KIRILLOV, V. P. BOBKOV, I. P. SMOGALEV, V. N. VINOGRA-DOV, X. C. HUANG, and E. ROYER, "The 1995 Look-Up Tables for Critical Heat Flux in Tubes," Nucl. Eng. Design, 163, 1, 1 (1996).
-
(1996)
Nucl. Eng. Design
, vol.163
, Issue.1
, pp. 1
-
-
Groeneveld, D.C.1
Leung, L.K.H.2
Kirillov, P.L.3
Bobkov, V.P.4
Smogalev, I.P.5
Vinogra-Dov, V.N.6
Huang, X.C.7
Royer, E.8
-
15
-
-
0034249270
-
Development of a code with the capability of internal assessment of uncertainty
-
Aug.
-
F. D'AURIA and W. GIANNOTTI, "Development of a Code with the Capability of Internal Assessment of Uncertainty," Nucl. Technol, 131, 1, 159 (Aug. 2000).
-
(2000)
Nucl. Technol
, vol.131
, Issue.1
, pp. 159
-
-
D'Auria, F.1
Giannotti, W.2
-
16
-
-
0036389754
-
Independent qualification of the CIAU tool based on the uncertainty estimate in the prediction of ANGRA 1 NPP inadvertent load rejection transient
-
Arlington, Virginia, April 14-18
-
R. C. BORGES, F. D'AURIA, and A. C. M. ALVIM, "Independent Qualification of the CIAU Tool Based on the Uncertainty Estimate in the Prediction of ANGRA 1 NPP Inadvertent Load Rejection Transient," ICONE 10, Arlington, Virginia, April 14-18, 2002.
-
(2002)
ICONE
, vol.10
-
-
Borges, R.C.1
D'Auria, F.2
Alvim, A.C.M.3
-
17
-
-
0027685412
-
Scaling of complex phenomena in system thermal hydraulics
-
Oct.
-
R. BOVALINI, F. D'AURIA, and G. M. GALASSI, "Scaling of Complex Phenomena in System Thermal Hydraulics," Nucl. Sci. Eng., 115, 89 (Oct. 1993).
-
(1993)
Nucl. Sci. Eng.
, vol.115
, pp. 89
-
-
Bovalini, R.1
D'Auria, F.2
Galassi, G.M.3
-
18
-
-
0000169692
-
Scaling of natural circulation in PWR systems
-
F. D'AURIA, G. M. GALASSI, P. VIGNI, and A. CALASTRI, "Scaling of Natural Circulation in PWR Systems," Nucl. Eng. Design, 132, 2, 187 (1992).
-
(1992)
Nucl. Eng. Design
, vol.132
, Issue.2
, pp. 187
-
-
D'Auria, F.1
Galassi, G.M.2
Vigni, P.3
Calastri, A.4
-
20
-
-
85039464801
-
Methodology of internal assessment of uncertainty for safety analysis code
-
Gatlinburg, Tennessee, April 6-10, 2003, American Nuclear Society
-
A. PETRUZZI, K. IVANOV, F. D'AURIA, and W. GIANNOTTI, "Methodology of Internal Assessment of Uncertainty for Safety Analysis Code," Proc. Int. Conf. Nuclear Mathematical and Computational Sciences, Gatlinburg, Tennessee, April 6-10, 2003, American Nuclear Society (2003).
-
(2003)
Proc. Int. Conf. Nuclear Mathematical and Computational Sciences
-
-
Petruzzi, A.1
Ivanov, K.2
D'Auria, F.3
Giannotti, W.4
-
21
-
-
85039463270
-
BWRTT activities at university of Pisa with main connection to phase III and the extreme scenarios
-
Barcelona, Spain, January 21-22
-
A. BOUSBIA SALAH, J. VEDOVI, G. M. GALASSI, and F. D'AURIA, "BWRTT Activities at University of Pisa with Main Connection to Phase III and the Extreme Scenarios," OECD/NRC Boiling Water Reactor Turbine Trip Benchmark, Fifth Workshop, Barcelona, Spain, January 21-22, 2003.
-
(2003)
OECD/NRC Boiling Water Reactor Turbine Trip Benchmark, Fifth Workshop
-
-
Bousbia Salah, A.1
Vedovi, J.2
Galassi, G.M.3
D'Auria, F.4
-
22
-
-
14544282673
-
-
NEA/NSC/DOE (June)
-
J. SOLIS, K. IVANOV, B. SARIKAYA, A. OLSON, and K. HUNT, "Boiling Water Reactor Turbine Trip Benchmark, Final Specifications," Vol. 1, No. 1, NEA/NSC/DOE (June 2001).
-
(2001)
Boiling Water Reactor Turbine Trip Benchmark, Final Specifications
, vol.1
, Issue.1
-
-
Solis, J.1
Ivanov, K.2
Sarikaya, B.3
Olson, A.4
Hunt, K.5
-
23
-
-
85039462984
-
A novel methodology of internal assessment of uncertainty for three-dimensional neutronics/thermal-hydraulics system codes
-
Paris, France, September 22-24, 2003, and NURETH-10, Seoul, Korea, October 5-9
-
A. PETRUZZI, F. D'AURIA, and K. IVANOV, "A Novel Methodology of Internal Assessment of Uncertainty for Three-Dimensional Neutronics/Thermal- Hydraulics System Codes," Proc. Int. Conf. Supercomputing in Nuclear Applications, Paris, France, September 22-24, 2003, and NURETH-10, Seoul, Korea, October 5-9, 2003.
-
(2003)
Proc. Int. Conf. Supercomputing in Nuclear Applications
-
-
Petruzzi, A.1
D'Auria, F.2
Ivanov, K.3
|