Year |
Citation |
Score |
2021 |
Abdel-Khalik HS, Trottier A, Serghiuta D, Huang D. UNCERTAINTY CHARACTERIZATION FRAMEWORK FOR STEADY-STATE AND TRANSIENT NEUTRONICS SIMULATIONS OF A CANDU REACTOR Epj Web of Conferences. 247: 15002. DOI: 10.1051/EPJCONF/202124715002 |
0.34 |
|
2020 |
Huang D, Abdel-Khalik HS. Application of Cross Sections Uncertainty Propagation Framework to Light and Heavy Water Reactor Systems Journal of Nuclear Engineering and Radiation Science. 6. DOI: 10.1115/1.4045032 |
0.349 |
|
2020 |
Huang D, Abdel-Khalik HS. Theoretical Development of Cross Section Uncertainty Library for Core Simulators Journal of Nuclear Engineering and Radiation Science. 6. DOI: 10.1115/1.4045031 |
0.4 |
|
2020 |
Seo J, Abdel-Khalik H, Perko Z. Addressing Ambiguities in Constrained Sensitivity Analysis for Reactor Physics Problems Nuclear Technology. 1-13. DOI: 10.1080/00295450.2020.1721407 |
0.316 |
|
2020 |
Huang D, Abdel-Khalik HS. Nuclear data uncertainty propagation and modeling uncertainty impact evaluation in neutronics core simulation Progress in Nuclear Energy. 128: 103443. DOI: 10.1016/J.Pnucene.2020.103443 |
0.502 |
|
2020 |
Huang D, Abdel-Khalik H. Modeling errors-preserving constrained sensitivity analysis Nuclear Engineering and Design. 365: 110729. DOI: 10.1016/J.Nucengdes.2020.110729 |
0.443 |
|
2020 |
Huang D, Mertyurek U, Abdel-Khalik H. Verification of the sensitivity and uncertainty-based criticality safety validation techniques: ORNL’s SCALE case study Nuclear Engineering and Design. 361: 110571. DOI: 10.1016/J.Nucengdes.2020.110571 |
0.442 |
|
2019 |
Wu Z, Liang J, Peng X, Abdel-Khalik HS. GPT-Free Sensitivity Analysis for Monte Carlo Models Nuclear Technology. 205: 912-927. DOI: 10.1080/00295450.2018.1556062 |
0.351 |
|
2017 |
Katano R, Endo T, Yamamoto A, Abdo M, Abdel-Khalik H. Estimation of sensitivity coefficients of core characteristics based on reduced-order modeling using sensitivity matrix of assembly characteristics Journal of Nuclear Science and Technology. 54: 637-647. DOI: 10.1080/00223131.2017.1299052 |
0.409 |
|
2017 |
Huang D, Abdel-Khalik H, Rabiti C, Gleicher F. Dimensionality reducibility for multi-physics reduced order modeling Annals of Nuclear Energy. 110: 526-540. DOI: 10.1016/J.Anucene.2017.06.045 |
0.431 |
|
2015 |
Wang C, Abdel-Khalik HS. Exact-to-precision generalized perturbation theory for neutron transport calculation Nuclear Engineering and Design. DOI: 10.1016/J.Nucengdes.2015.07.024 |
0.414 |
|
2015 |
Khuwaileh BA, Abdel-Khalik HS. Subspace-based Inverse Uncertainty Quantification for Nuclear Data Assessment Nuclear Data Sheets. 123: 57-61. DOI: 10.1016/J.Nds.2014.12.010 |
0.414 |
|
2015 |
Arbanas G, Williams ML, Leal LC, Dunn ME, Khuwaileh BA, Wang C, Abdel-Khalik H. Advancing Inverse Sensitivity/Uncertainty Methods for Nuclear Fuel Cycle Applications Nuclear Data Sheets. 123: 51-56. DOI: 10.1016/J.Nds.2014.12.009 |
0.523 |
|
2015 |
Wang C, Abdel-Khalik HS, Mertyurek U. CRANE: A new SCALE super-sequence for neutron transport calculations 5th Topical Meeting On Advances in Nuclear Fuel Management, Anfm 2015: Advances in Nuclear Fuel Management V. 452-462. |
0.752 |
|
2014 |
Zhang Q, Abdel-Khalik HS. Global variance reduction for Monte Carlo reactor physics calculations Nuclear Engineering and Design. 280: 76-85. DOI: 10.1016/J.Nucengdes.2014.08.027 |
0.459 |
|
2014 |
Athe P, Mertyurek U, Abdel-Khalik HS. Determination of bias, bias uncertainty, and coverage using data assimilation Transactions of the American Nuclear Society. 111: 1299-1302. |
0.752 |
|
2013 |
Wu Z, Abdel-Khalik HS. Hybrid biasing approaches for global variance reduction. Applied Radiation and Isotopes : Including Data, Instrumentation and Methods For Use in Agriculture, Industry and Medicine. 72: 83-8. PMID 23208236 DOI: 10.1016/J.Apradiso.2012.09.026 |
0.326 |
|
2013 |
Bang Y, Abdel-Khalik HS, Jessee MA, Mertyurek U. Hybrid reduced order modeling for assembly calculations International Conference On Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013. 3: 2028-2039. DOI: 10.1016/j.nucengdes.2015.07.020 |
0.777 |
|
2013 |
Bang Y, Abdel-Khalik HS, Jessee MA, Mertyurek U. Hybrid reduced order modeling for assembly calculations International Conference On Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013. 3: 2028-2039. DOI: 10.1016/J.Nucengdes.2015.07.020 |
0.778 |
|
2013 |
Wang C, Abdel-Khalik HS. Exact-to-precision generalized perturbation theory for eigenvalue problems Nuclear Engineering and Design. 256: 130-140. DOI: 10.1016/J.Nucengdes.2012.11.006 |
0.436 |
|
2013 |
Abdel-Khalik HS, Bang Y, Wang C. Overview of hybrid subspace methods for uncertainty quantification, sensitivity analysis Annals of Nuclear Energy. 52: 28-46. DOI: 10.1016/J.Anucene.2012.07.020 |
0.607 |
|
2013 |
Bang Y, Abdel-Khalik HS. Projection-based second order perturbation theory Annals of Nuclear Energy. 52: 80-85. DOI: 10.1016/J.Anucene.2012.07.009 |
0.538 |
|
2013 |
Bang Y, Abdel-Khalik HS. Hybrid reduced order modeling algorithms for reactor physics calculations, invited, mark mills award winner Transactions of the American Nuclear Society. 109: 1385-1388. |
0.453 |
|
2013 |
Wang C, Abdel-Khalik HS. Exact-to-precision generalized perturbation for neutron transport calculation International Conference On Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013. 2: 828-841. |
0.324 |
|
2012 |
Abdel-Khalik HS, Bang Y, Kennedy C, Hite J. Reduced Order Modeling For Nonlinear Multi-Component Models International Journal For Uncertainty Quantification. 2: 341-361. DOI: 10.1615/Int.J.Uncertaintyquantification.2012003523 |
0.568 |
|
2012 |
Kennedy C, Rabiti C, Abdel-Khalik H. Generalized Perturbation Theory-Free Sensitivity Analysis for Eigenvalue Problems Nuclear Technology. 179: 169-179. DOI: 10.13182/Nt179-169 |
0.371 |
|
2012 |
Wu Z, Zhang Q, Abdel-Khalik H. Hybrid Monte Carlo-Deterministic Methods For Reactor Analysis Nuclear Technology. 180: 372-382. DOI: 10.13182/Nt12-A15350 |
0.388 |
|
2012 |
Bang Y, Wang C, Abdel-Khalik HS. State-Based Adjoint Method for Reduced Order Modeling Transport Theory and Statistical Physics. 41: 101-132. DOI: 10.1080/00411450.2012.672359 |
0.577 |
|
2012 |
Abdel-Khalik HS. Adjoint-based sensitivity analysis for multi-component models Nuclear Engineering and Design. 245: 49-54. DOI: 10.1016/J.Nucengdes.2012.01.017 |
0.379 |
|
2012 |
Bang Y, Abdel-Khalik HS, Hite JM. Hybrid reduced order modeling applied to nonlinear models International Journal For Numerical Methods in Engineering. 91: 929-949. DOI: 10.1002/Nme.4298 |
0.563 |
|
2012 |
Bang Y, Abdel-Khalik HS. A surrogate-based uncertainty quantification with quantifiable errors International Conference On the Physics of Reactors 2012, Physor 2012: Advances in Reactor Physics. 4: 2916-2930. |
0.522 |
|
2012 |
Bang Y, Abdel-Khalik HS. Reduced order modeling for multi-physics problems Transactions of the American Nuclear Society. 107: 586-588. |
0.42 |
|
2011 |
Jessee MA, Turinsky PJ, Abdel-Khalik HS. Many-group cross-section adjustment techniques for boiling water reactor adaptive simulation Nuclear Science and Engineering. 169: 40-55. DOI: 10.13182/Nse09-67 |
0.802 |
|
2011 |
Bang Y, Abdel-Khalik HS. State-based adjoint model reduction for large scale control problems Proceedings - Isrcs 2011: 4th International Symposium On Resilient Control Systems. 69-74. DOI: 10.1109/ISRCS.2011.6016091 |
0.493 |
|
2011 |
Wang C, Abdel-Khalik HS. Exact-to-precision generalized perturbation theory for source-driven systems Nuclear Engineering and Design. 241: 5104-5112. DOI: 10.1016/J.Nucengdes.2011.09.009 |
0.545 |
|
2011 |
Bang Y, Kennedy C, Abdel-Khalik HS. On the propagation of uncertainties in high dimensional models Transactions of the American Nuclear Society. 105: 468-472. |
0.448 |
|
2011 |
Bang Y, Abdel-Khalik HS. ESM-based regularized hessian construction algorithm Transactions of the American Nuclear Society. 104: 374-375. |
0.377 |
|
2011 |
Bang Y, Abdel-Khalik HS. Regression-based approach for second order perturbation theory Transactions of the American Nuclear Society. 105: 805-807. |
0.405 |
|
2011 |
Bang Y, Abdel-Khalik HS. Verification tests for uncertainty quantification and sensitivity analysis studies Transactions of the American Nuclear Society. 105: 451-453. |
0.408 |
|
2011 |
Bang Y, Abdel-Khalik HS. Response surface modeling with subspace-enhanced regression analysis Transactions of the American Nuclear Society. 105: 458-460. |
0.385 |
|
2009 |
Stover TE, Turinsky PJ, Bays SE, Abdel-Khalik HS, Iqbal M. Integral parameter sensitivity, uncertainty, and representativity of a fast critical experiment with regard to a gen-IV fast reactor concept American Nuclear Society - 4th Topical Meeting On Advances in Nuclear Fuel Management 2009, Anfm Iv. 2: 1202-1221. |
0.764 |
|
2009 |
Jessee MA, Turinsky PJ, Abdel-Khalik HS. Cross-section uncertainty propagation and adjustment algorithms for BWR core simulation American Nuclear Society - 4th Topical Meeting On Advances in Nuclear Fuel Management 2009, Anfm Iv. 2: 1357-1376. |
0.802 |
|
2008 |
Abdel-Khalik HS, Turinsky PJ, Jessee MA. Efficient subspace methods-based algorithms for performing sensitivity, uncertainty, and adaptive simulation of large-scale computational models Nuclear Science and Engineering. 159: 256-272. DOI: 10.13182/Nse159-256 |
0.801 |
|
2008 |
Abdel-Khalik H, Turinsky P, Jessee M, Elkins J, Stover T, Iqbal M. Uncertainty Quantification, Sensitivity Analysis, and Data Assimilation for Nuclear Systems Simulation Nuclear Data Sheets. 109: 2785-2790. DOI: 10.1016/J.Nds.2008.11.010 |
0.757 |
|
2008 |
Abdel-Khalik HS, Hovland PD, Lyons A, Stover TE, Utke J. A low rank approach to automatic differentiation Lecture Notes in Computational Science and Engineering. 64: 55-65. DOI: 10.1007/978-3-540-68942-3_6 |
0.761 |
|
2008 |
Jessee MA, Abdel-Khalik HS, Turinsky PJ. Cross-section adjustment algorithms for boiling water reactor core simulation Transactions of the American Nuclear Society. 99: 755-757. |
0.768 |
|
2007 |
Jessee MA, Abdel-Khalik HS, Turinsky PJ. Subspace methods for multi-scale/multi-physics calculations, part II: Numerical experiments Transactions of the American Nuclear Society. 96: 551-552. |
0.76 |
|
2007 |
Abdel-Khalik HS, Turinsky PJ. Subspace methods for multi-scale/multi-physics calculations, part I: theory Transactions of the American Nuclear Society. 96: 548-550. |
0.632 |
|
2007 |
Stover TE, Abdel-Khalik HS, Turinsky PJ. Quantification of back-end fuel cycle metrics uncertainties Transactions of the American Nuclear Society. 96: 523-525. |
0.73 |
|
2007 |
Jessee MA, Abdel-Khalik HS, Turinsky PJ. Evaluation of BWR core attributes uncertainties due to multi-group cross-section uncertainties Joint International Topical Meeting On Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + Sna 2007. |
0.8 |
|
2007 |
Dunzik-Gougar ML, Juchau CA, Pasamehmetoglu K, Wilson PPH, Oliver KM, Turinsky PJ, Abdel-Khalik HS, Hays R, Stover TE. Global Evaluation of Nuclear Infrastructure Utilization Scenarios (GENIUS) Global 2007: Advanced Nuclear Fuel Cycles and Systems. 1604-1611. |
0.752 |
|
2005 |
Abdel-Khalik HS, Turinsky PJ. Adaptive core simulation employing discrete inverse theory - Part II: Numerical experiments Nuclear Technology. 151: 22-34. DOI: 10.13182/Nt05-A3628 |
0.699 |
|
2005 |
Abdel-Khalik HS, Turinsky PJ. Adaptive core simulation employing discrete inverse theory - Part I: Theory Nuclear Technology. 151: 9-21. DOI: 10.13182/Nt05-A3627 |
0.706 |
|
2005 |
Abdel-Khalik HS, Turinsky PJ. Evaluation of core attributes uncertainties due to input data uncertainties Transactions of the American Nuclear Society. 92: 546-547. |
0.654 |
|
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