-
1
-
-
57049182499
-
Uncertainty quantification, sensitivity analysis, and data assimilation for nuclear systems simulation
-
Abdel-Khalik H., Turinsky P., Jessee M., Elkins J., Stover T., and Iqbal M. Uncertainty quantification, sensitivity analysis, and data assimilation for nuclear systems simulation. Nucl. Data Sheets 109 (2008) 2785-2790
-
(2008)
Nucl. Data Sheets
, vol.109
, pp. 2785-2790
-
-
Abdel-Khalik, H.1
Turinsky, P.2
Jessee, M.3
Elkins, J.4
Stover, T.5
Iqbal, M.6
-
2
-
-
0027677011
-
Sensitivity analysis of thermohydraulic systems via generalized perturbation theory (HGPT) methods
-
Andrade Lima F.R., Brayner de Oliveira Lira C.A., and Gandini A. Sensitivity analysis of thermohydraulic systems via generalized perturbation theory (HGPT) methods. Ann. Nucl. Energy 20 10 (1993) 679-690
-
(1993)
Ann. Nucl. Energy
, vol.20
, Issue.10
, pp. 679-690
-
-
Andrade Lima, F.R.1
Brayner de Oliveira Lira, C.A.2
Gandini, A.3
-
3
-
-
0017555701
-
Mass transfer in turbulent pipe flow measured by electrochemical method
-
Berger F.P., and Hau K. Mass transfer in turbulent pipe flow measured by electrochemical method. Int. J. Heat Mass Transfer 20 (1977) 1185
-
(1977)
Int. J. Heat Mass Transfer
, vol.20
, pp. 1185
-
-
Berger, F.P.1
Hau, K.2
-
4
-
-
33646103663
-
Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal-hydraulic 3D kinetics code
-
Bousbia Salah A., Kliem S., Rohde U., D'Auria F., and Petruzzi A. Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal-hydraulic 3D kinetics code. Nucl. Eng. Des. 236 (2006) 1240-1255
-
(2006)
Nucl. Eng. Des.
, vol.236
, pp. 1240-1255
-
-
Bousbia Salah, A.1
Kliem, S.2
Rohde, U.3
D'Auria, F.4
Petruzzi, A.5
-
5
-
-
49549171636
-
Mechanism of detachment of colloidal particles from a flat substrate in turbulent flow
-
Cleaver J.W., and Yates B. Mechanism of detachment of colloidal particles from a flat substrate in turbulent flow. J. Coll. Interf. Sci. 44 (1973) 464-474
-
(1973)
J. Coll. Interf. Sci.
, vol.44
, pp. 464-474
-
-
Cleaver, J.W.1
Yates, B.2
-
6
-
-
55049132746
-
Uncertainty and sensitivity analysis of the LOFT L2-5 test: results of the BEMUSE programme
-
de Crécy A., Bazin P., Glaeser H., Skorek T., Joucla J., Probst P., Fujioka K., Chung B.D., Oh D.Y., Kyncl M., Pernica R., Macek J., Meca R., Macian R., D'Auria F., Petruzzi A., Batet L., Perez M., and Reventos F. Uncertainty and sensitivity analysis of the LOFT L2-5 test: results of the BEMUSE programme. Nucl. Eng. Des. 238 (2008) 3561-3578
-
(2008)
Nucl. Eng. Des.
, vol.238
, pp. 3561-3578
-
-
de Crécy, A.1
Bazin, P.2
Glaeser, H.3
Skorek, T.4
Joucla, J.5
Probst, P.6
Fujioka, K.7
Chung, B.D.8
Oh, D.Y.9
Kyncl, M.10
Pernica, R.11
Macek, J.12
Meca, R.13
Macian, R.14
D'Auria, F.15
Petruzzi, A.16
Batet, L.17
Perez, M.18
Reventos, F.19
-
7
-
-
0033133806
-
Modeling and simulation of corrosion product activity in pressurized water reactors under power perturbations
-
Deeba F., Mirza A.M., and Mirza N.M. Modeling and simulation of corrosion product activity in pressurized water reactors under power perturbations. Ann. Nucl. Energy 26 7 (1999) 561-578
-
(1999)
Ann. Nucl. Energy
, vol.26
, Issue.7
, pp. 561-578
-
-
Deeba, F.1
Mirza, A.M.2
Mirza, N.M.3
-
8
-
-
0036489486
-
Parameter sensitivities in nuclear reaction cross-section calculations
-
Fessler A., and Smith D.L. Parameter sensitivities in nuclear reaction cross-section calculations. Ann. Nucl. Energy 29 (2002) 363-384
-
(2002)
Ann. Nucl. Energy
, vol.29
, pp. 363-384
-
-
Fessler, A.1
Smith, D.L.2
-
9
-
-
40649126604
-
Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations
-
García-Herranz N., Cabellos O., Sanz J., Juan J., and Kuijper J.C. Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations. Ann. Nucl. Energy 35 (2008) 714-730
-
(2008)
Ann. Nucl. Energy
, vol.35
, pp. 714-730
-
-
García-Herranz, N.1
Cabellos, O.2
Sanz, J.3
Juan, J.4
Kuijper, J.C.5
-
10
-
-
0024837267
-
A sensitivity analysis of multicriteria choice-methods: an application on the basis of the optimal site selection for a nuclear power plant
-
Hartog J.A., Hinloopen E., and Nijkamp P. A sensitivity analysis of multicriteria choice-methods: an application on the basis of the optimal site selection for a nuclear power plant. Energy Econ. 11 4 (1989) 293-300
-
(1989)
Energy Econ.
, vol.11
, Issue.4
, pp. 293-300
-
-
Hartog, J.A.1
Hinloopen, E.2
Nijkamp, P.3
-
12
-
-
0003513729
-
-
Jaeger R.G. (Ed), Springer-Verlag, New York
-
In: Jaeger R.G. (Ed). Engineering Compendium on Radiation Shielding vol. III (1970), Springer-Verlag, New York
-
(1970)
Engineering Compendium on Radiation Shielding
, vol.III
-
-
-
13
-
-
34248665304
-
Uncertainty and sensitivity analysis for steady-state thermal-hydraulics of research reactors
-
Kazeminejad H. Uncertainty and sensitivity analysis for steady-state thermal-hydraulics of research reactors. Prog. Nucl. Energy 49 (2007) 313-322
-
(2007)
Prog. Nucl. Energy
, vol.49
, pp. 313-322
-
-
Kazeminejad, H.1
-
14
-
-
0027336929
-
Stochastic sensitivity analysis of the biosphere model for Canadian nuclear fuel waste management
-
Keith Reid J.A., and Corbett B.J. Stochastic sensitivity analysis of the biosphere model for Canadian nuclear fuel waste management. Waste Manage. 13 2 (1993) 181-194
-
(1993)
Waste Manage.
, vol.13
, Issue.2
, pp. 181-194
-
-
Keith Reid, J.A.1
Corbett, B.J.2
-
15
-
-
0020251642
-
A sensitivity study of seismic structure-soil structure interaction problems for nuclear power plants
-
Matthees W., and Magiera G. A sensitivity study of seismic structure-soil structure interaction problems for nuclear power plants. Nucl. Energy Des. 73 3 (1982) 343-363
-
(1982)
Nucl. Energy Des.
, vol.73
, Issue.3
, pp. 343-363
-
-
Matthees, W.1
Magiera, G.2
-
16
-
-
0032048213
-
Simulation of corrosion product activity in pressurized water reactors under flow rate transients
-
Mirza A.M., Mirza N.M., and Mir I. Simulation of corrosion product activity in pressurized water reactors under flow rate transients. Ann. Nucl. Energy 25 6 (1998) 331-345
-
(1998)
Ann. Nucl. Energy
, vol.25
, Issue.6
, pp. 331-345
-
-
Mirza, A.M.1
Mirza, N.M.2
Mir, I.3
-
17
-
-
0037404275
-
Computer simulation of corrosion product activity in primary coolants of a typical PWR under flow rate transients and linearly accelerating corrosion
-
Mirza N.M., Rafique M., Hyder M.J., and Mirza S.M. Computer simulation of corrosion product activity in primary coolants of a typical PWR under flow rate transients and linearly accelerating corrosion. Ann. Nucl. Energy 30 7 (2003) 831-851
-
(2003)
Ann. Nucl. Energy
, vol.30
, Issue.7
, pp. 831-851
-
-
Mirza, N.M.1
Rafique, M.2
Hyder, M.J.3
Mirza, S.M.4
-
18
-
-
14844317638
-
Simulation of corrosion product activity for nonlinearly rising corrosion on inner surfaces of primary coolant pipes of a typical PWR under flow rate transients
-
Mirza N.M., Rafique M., Mirza S.M., and Hyder M.J. Simulation of corrosion product activity for nonlinearly rising corrosion on inner surfaces of primary coolant pipes of a typical PWR under flow rate transients. Appl. Radiat. Isotopes 62 5 (2005) 681-692
-
(2005)
Appl. Radiat. Isotopes
, vol.62
, Issue.5
, pp. 681-692
-
-
Mirza, N.M.1
Rafique, M.2
Mirza, S.M.3
Hyder, M.J.4
-
19
-
-
0021035792
-
The implication of sensitivity analysis on the safety and delayed neutron parameters for fast breeder reactors
-
Onega R.J., and Florian R.J. The implication of sensitivity analysis on the safety and delayed neutron parameters for fast breeder reactors. Ann. Nucl. Energy 10 9 (1983) 477-490
-
(1983)
Ann. Nucl. Energy
, vol.10
, Issue.9
, pp. 477-490
-
-
Onega, R.J.1
Florian, R.J.2
-
20
-
-
0028499050
-
The adjoint sensitivity method, a contribution to the code uncertainty evaluation
-
Ounsy A., Mrun B., and de Crećy F. The adjoint sensitivity method, a contribution to the code uncertainty evaluation. Nucl. Eng. Des. 149 1-3 (1994) 357-364
-
(1994)
Nucl. Eng. Des.
, vol.149
, Issue.1-3
, pp. 357-364
-
-
Ounsy, A.1
Mrun, B.2
de Crećy, F.3
-
21
-
-
61549124394
-
A global approach to the physics validation of simulation codes for future nuclear systems
-
Palmiotti G., Salvtores M., Aliberti G., Hiruta H., McKnight R., Oblozinsky P., and Yang W.S. A global approach to the physics validation of simulation codes for future nuclear systems. Ann. Nucl. Energy 36 (2009) 355-361
-
(2009)
Ann. Nucl. Energy
, vol.36
, pp. 355-361
-
-
Palmiotti, G.1
Salvtores, M.2
Aliberti, G.3
Hiruta, H.4
McKnight, R.5
Oblozinsky, P.6
Yang, W.S.7
-
22
-
-
31144461236
-
RELAP5/MOD3.2 sensitivity calculation of loss-of-feed water (LOFW) transient at unit 6 of Kozloduy NPP
-
Pavlova M.P., Groudev P.P., Stefanova A.E., and Gencheva R.V. RELAP5/MOD3.2 sensitivity calculation of loss-of-feed water (LOFW) transient at unit 6 of Kozloduy NPP. Nucl. Eng. Des. 236 3 (2006) 322-331
-
(2006)
Nucl. Eng. Des.
, vol.236
, Issue.3
, pp. 322-331
-
-
Pavlova, M.P.1
Groudev, P.P.2
Stefanova, A.E.3
Gencheva, R.V.4
-
23
-
-
0022925975
-
An automated sensitivity analysis procedure for the performance assessment of nuclear waste isolation systems
-
Pin F.G., Worley B.A., Oblow E.M., Wright R.Q., and Harper W.V. An automated sensitivity analysis procedure for the performance assessment of nuclear waste isolation systems. Nucl. Chem. Waste Manage. 6 3, 4 (1986) 255-263
-
(1986)
Nucl. Chem. Waste Manage.
, vol.6
, Issue.3-4
, pp. 255-263
-
-
Pin, F.G.1
Worley, B.A.2
Oblow, E.M.3
Wright, R.Q.4
Harper, W.V.5
-
24
-
-
27344442304
-
Kinetic study of corrosion product activity in primary coolant pipes of a typical PWR under flow rate transients and linearly increasing corrosion rates
-
Rafique M., Mirza N.M., and Mirza S.M. Kinetic study of corrosion product activity in primary coolant pipes of a typical PWR under flow rate transients and linearly increasing corrosion rates. J. Nucl. Mater. 346 2, 3 (2005) 282-292
-
(2005)
J. Nucl. Mater.
, vol.346
, Issue.2-3
, pp. 282-292
-
-
Rafique, M.1
Mirza, N.M.2
Mirza, S.M.3
-
25
-
-
66749091658
-
Simulation and modeling of radioactivity buildup due to corrosion products in ion-exchanger and filters of a typical PWR
-
Rafique M., Mirza N.M., and Mirza S.M. Simulation and modeling of radioactivity buildup due to corrosion products in ion-exchanger and filters of a typical PWR. Radiochemistry 51 1 (2009) 47-54
-
(2009)
Radiochemistry
, vol.51
, Issue.1
, pp. 47-54
-
-
Rafique, M.1
Mirza, N.M.2
Mirza, S.M.3
-
26
-
-
4243565006
-
Spaciation and analysis of corrosion products in the primary coolant of pressurized water reactors
-
Raymond A., de Murcia A., and Dhaunt S. Spaciation and analysis of corrosion products in the primary coolant of pressurized water reactors. Anal. Chem. Acta 195 (1987) 265
-
(1987)
Anal. Chem. Acta
, vol.195
, pp. 265
-
-
Raymond, A.1
de Murcia, A.2
Dhaunt, S.3
-
28
-
-
0001244976
-
Sensitivity analysis as an ingredient of modeling
-
Saltelli A., Tarantola S., and Campolongo F. Sensitivity analysis as an ingredient of modeling. Stat. Sci. 15 4 (2000) 377-395
-
(2000)
Stat. Sci.
, vol.15
, Issue.4
, pp. 377-395
-
-
Saltelli, A.1
Tarantola, S.2
Campolongo, F.3
-
29
-
-
49649136321
-
Systems analysis of dual purpose nuclear power and desalting plants - part II: sensitivity analysis
-
Stamet L.E., Fan L.T., and Hwang C.L. Systems analysis of dual purpose nuclear power and desalting plants - part II: sensitivity analysis. Desalination 11 2 (1972) 239-254
-
(1972)
Desalination
, vol.11
, Issue.2
, pp. 239-254
-
-
Stamet, L.E.1
Fan, L.T.2
Hwang, C.L.3
-
30
-
-
55949100424
-
Sensitivity analysis for delayed neutron data
-
van Rooijen W.F.G., and Lathouwers D. Sensitivity analysis for delayed neutron data. Ann. Nucl. Energy 35 (2008) 2186-2194
-
(2008)
Ann. Nucl. Energy
, vol.35
, pp. 2186-2194
-
-
van Rooijen, W.F.G.1
Lathouwers, D.2
-
32
-
-
0021466762
-
Application of adjoint sensitivity analysis to nuclear reactor fuel rod performance
-
Wildeman S.J., and Was G.S. Application of adjoint sensitivity analysis to nuclear reactor fuel rod performance. Nucl. Eng. Des. 80 1 (1984) 27-38
-
(1984)
Nucl. Eng. Des.
, vol.80
, Issue.1
, pp. 27-38
-
-
Wildeman, S.J.1
Was, G.S.2
|