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Alireza Haghighat - Publications

Affiliations: 
1996-2001 Pennsylvania State University, State College, PA, United States 
 2001-2011 University of Florida, Gainesville, Gainesville, FL, United States 
 2011- Virginia Polytechnic Institute and State University, Blacksburg, VA, United States 
Area:
Nuclear Engineering
Website:
http://www.nuclear.me.vt.edu/Faculty_Staff/bios/bio_AlirezaHaghighat.html
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31 high-probability publications. We are testing a new system for linking publications to authors. You can help! If you notice any inaccuracies, please sign in and mark papers as correct or incorrect matches. If you identify any major omissions or other inaccuracies in the publication list, please let us know.

Year Citation  Score
2018 Walters WJ, Roskoff NJ, Haghighat A. The RAPID Fission Matrix Approach to Reactor Core Criticality Calculations Nuclear Science and Engineering. 192: 21-39. DOI: 10.1080/00295639.2018.1497395  0.429
2017 Walters WJ, Haghighat A. The adaptive collision source method for discrete ordinates radiation transport Annals of Nuclear Energy. 105: 45-58. DOI: 10.1016/J.Anucene.2017.02.013  0.487
2016 Royston K, Haghighat A, Yi C. Application of TITAN for Simulation of Particle Streaming in a Duct Epj Web of Conferences. 106. DOI: 10.1051/epjconf/201610603007  0.359
2016 Haghighat A, Royston K, Walters W. MRT methodologies for real-time simulation of nonproliferation and safeguards problems Annals of Nuclear Energy. 87: 61-67. DOI: 10.1016/J.Anucene.2015.06.004  0.444
2014 Haghighat A, Royston K, Sjoden G. Unique formulations in TITAN and PENTRAN for medical physics applications (The 12th International Conference on Radiation Shielding (ICRS-12) and the 17th Topical Meeting of the Radiation Protection and Shielding Division of ANS (RPSD-2012)) -- (Workshop on Computational Medical Physics) Progress in Nuclear Science and Technology. 4: 883-887. DOI: 10.15669/Pnst.4.883  0.735
2014 Walters W, Haghighat A, Royston K. A response function methodology to calculate induced fission neutron flux distribution in an active interrogation system (The 12th International Conference on Radiation Shielding (ICRS-12) and the 17th Topical Meeting of the Radiation Protection and Shielding Division of ANS (RPSD-2012)) -- (Deterministic Methods and Applications) Progress in Nuclear Science and Technology. 4: 533-537. DOI: 10.15669/Pnst.4.533  0.467
2014 Royston K, Haghighat A, Walters W, Yi C, Sjoden G. Determination of current at a detector window using a hybrid adjoint function methodology Progress in Nuclear Science and Technology. 4: 528-532. DOI: 10.15669/Pnst.4.528  0.762
2012 Walters W, Haghighat A, Sitaraman S, Ham Y. Development of INSPCT-S for inspection of spent fuel pool Astm Special Technical Publication. 1550: 690-705. DOI: 10.1520/Jai104070  0.45
2012 Wenner MT, Haghighat A, Adams JM, Carlson AD, Grimes SM, Massey TN. Novel investigation of iron cross sections via spherical shell transmission measurements and particle transport calculations for material embrittlement studies Nuclear Science and Engineering. 170: 207-233. DOI: 10.13182/Nse09-30  0.413
2010 Royston KK, Haghighat A, Yi C, Cebula A, Gilland D. Validation of a new deterministic transport code for SPECT simulation Ieee Nuclear Science Symposium Conference Record. 3018-3021. DOI: 10.1109/NSSMIC.2010.5874352  0.305
2006 Longoni G, Haghighat A, Yi C, Sjoden G. Benchmarking of PENTRAN-SSN Parallel Transport Code and FAST Preconditioning Algorithm Using the VENUS-2 MOX-Fueled Benchmark Problem Journal of Astm International. 3: 1-10. DOI: 10.1520/Jai13428  0.741
2006 Wenner M, Haghighat A, Grimes S, Massey T, Carlson A, Adams J. A New Methodology for Adjustment of Iron Scattering Cross Sections Using Time-of-Flight Spectroscopy Journal of Astm International. 3: 1-7. DOI: 10.1520/Jai100377  0.413
2005 Shedlock D, Haghighat A. Neutron analysis of spent fuel storage installation using parallel computing and advance discrete ordinates and Monte Carlo techniques. Radiation Protection Dosimetry. 116: 662-6. PMID 16604721 DOI: 10.1093/Rpd/Nci226  0.37
2005 Omura M, Miyake Y, Hasegawa T, Ueki K, Sato O, Haghighat A, Sjoden GE. Performance of the improved version of monte Carlo code A3MCNP for large-scale shielding problems. Radiation Protection Dosimetry. 116: 493-7. PMID 16604685 DOI: 10.1093/rpd/nci160  0.753
2005 Miyake Y, Ohmura M, Hasegawa T, Ueki K, Sato O, Haghighat A, Sjoden GE. Performance of the improved version of the Monte Carlo A3MCNP code in the design of cask shielding Packaging, Transport, Storage & Security of Radioactive Material. 16: 229-236. DOI: 10.1179/174650905775295260  0.704
2005 Massey TN, Grimes SM, Wenner MT, Haghighat A, Adams JM, Carlson AD. Measurement of neutron transmission through iron spheres Aip Conference Proceedings. 769: 480-483. DOI: 10.1063/1.1945052  0.324
2004 Longoni G, Haghighat A, Sjoden G. A New Synthetic Acceleration Technique Based on the Simplified Even-Parity SNEquations Transport Theory and Statistical Physics. 33: 347-360. DOI: 10.1081/Tt-200051946  0.721
2004 Miyake Y, Ohmura M, Hasegawa T, Ueki K, Sato O, Haghighat A, Sjoden G. Improvement of Monte Carlo Code A3MCNP for Large-Scale Shielding Problems Journal of Nuclear Science and Technology. 41: 93-96. DOI: 10.1080/00223131.2004.10875653  0.713
2003 Haghighat A, Wagner JC. Monte Carlo variance reduction with deterministic importance functions Progress in Nuclear Energy. 42: 25-53. DOI: 10.1016/S0149-1970(02)00002-1  0.381
2002 Haghighat A, Gardner SR, Kucukboyaci V, Wenner MT, Adams JM, Carlson AD, Grimes SM, Massey TN. New Particle Transport Methods for Design and Optimization of Spherical-Shell Transmission Measurements Journal of Nuclear Science and Technology. 39: 1017-1020. DOI: 10.1080/00223131.2002.10875274  0.76
2002 Adams JM, Alpan A, Carlson AD, Gardner SR, Grimes SM, Haghighat A, Kucukboyaci V, Massey TN, Patchimpattapong A, Wenner MT. A New Investigation of Iron Cross Sections via Spherical-Shell Transmission Measurements and Particle Transport Calculations Journal of Nuclear Science and Technology. 2: 892-895. DOI: 10.1080/00223131.2002.10875242  0.554
2001 Haghighat A, Sjoden GE, Kucukboyaci VN. Effectiveness of pentran™'s unique numerics for simulation of the Kobayashi benchmarks Progress in Nuclear Energy. 39: 191-206. DOI: 10.1016/S0149-1970(01)00012-9  0.729
1998 Wagner JC, Haghighat A. Automated variance reduction of Monte Carlo shielding calculations using the discrete ordinates adjoint function Nuclear Science and Engineering. 128: 186-208. DOI: 10.13182/Nse98-2  0.442
1996 Wagner JC, Haghighat A, Petrovic BG. Monte Carlo transport calculations and analysis for reactor pressure vessel neutron fluence Nuclear Technology. 114: 373-398. DOI: 10.13182/Nt96-A35241  0.477
1996 Petrović BG, Haghighat A. Analysis of inherent oscillations in multidimensional SN solutions of the neutron transport equation Nuclear Science and Engineering. 124: 31-62. DOI: 10.13182/Nse96-A24222  0.313
1996 Petrovic BG, Haghighat A. Effects of SN method numerics on pressure vessel neutron fluence calculations Nuclear Science and Engineering. 122: 167-193. DOI: 10.13182/Nse96-3  0.431
1995 Haghighat A, Mahgerefteh M, Petrovic BG. Evaluation of the uncertainties in the source distribution for pressure vessel neutron fluence calculations Nuclear Technology. 109: 54-75. DOI: 10.13182/Nt95-A35068  0.395
1995 Haghighat A, Hunter MA, Mattis RE. Iterative schemes for parallel Sn algorithms in a shared-memory computing environment Nuclear Science and Engineering. 121: 103-113. DOI: 10.13182/Nse95-A24132  0.316
1993 Haghighat A, Veerasingam R. Transport analysis of several cross-section libraries used for reactor pressure vessel fluence calculations Nuclear Technology. 101: 237-243. DOI: 10.13182/Nt93-A34785  0.48
1991 Haghighat A. Angular parallelization of a curvilinear S sub n transport theory method Nuclear Science and Engineering. 108: 267-277. DOI: 10.13182/Nse91-A23824  0.364
1989 Haghighat A, Kosály G. Determination of the Field of View of a Boiling Water Reactor In-Core Detector Nuclear Science and Engineering. 101: 8-25. DOI: 10.13182/Nse89-A23591  0.666
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