Year |
Citation |
Score |
2015 |
Lee D, Kozlowski T, Downar TJ. Multi-group SP3 approximation for simulation of a three-dimensional PWR rod ejection accident Annals of Nuclear Energy. 77: 94-100. DOI: 10.1016/J.Anucene.2014.10.019 |
0.616 |
|
2014 |
Seker V, Downar TJ. Validation of AGREE with HTTR control rod withdrawal tests Transactions of the American Nuclear Society. 110: 416-418. |
0.64 |
|
2013 |
Li LS, Wang K, Collins B, Xu YL, Downar T. Developing and coupling of steady state two-phase thermal-hydraulic solver PATHS for PARCS Energy Science and Technology. 47: 295-298. DOI: 10.7538/Yzk.2013.47.S0.0295 |
0.36 |
|
2013 |
Tak NI, Kim MH, Lim HS, Noh JM, Drzewiecki TJ, Seker V, Downar TJ, Kelly J. Validation of numerical methods to calculate bypass flow in a prismatic gas-cooled reactor core Nuclear Engineering and Technology. 45: 745-752. DOI: 10.5516/Net.02.2013.521 |
0.702 |
|
2013 |
Park HH, Saller T, Seker V, Downar TJ. Neutronics analysis of the high temperature engineering test reactor (HTTR) Transactions of the American Nuclear Society. 108: 799-802. |
0.669 |
|
2012 |
Gajev I, Kozlowski T, Xu Y, Downar T. Sensitivity and uncertainty of OECD benchmark ringhals-1 TRACE/PARCS stability prediction Nuclear Technology. 180: 383-398. DOI: 10.13182/Nt12-A15351 |
0.646 |
|
2012 |
Yankov A, Collins B, Klein M, Jessee MA, Zwermann W, Velkov K, Pautz A, Downar T. A two-step approach to uncertainty quantification of core simulators Science and Technology of Nuclear Installations. 2012. DOI: 10.1155/2012/767096 |
0.365 |
|
2012 |
Brown NR, Seker V, Revankar ST, Downar TJ. Transient simulation of an endothermic chemical process facility coupled to a high temperature reactor: Model development and validation Nuclear Engineering and Design. 248: 1-13. DOI: 10.1016/J.Nucengdes.2012.03.049 |
0.703 |
|
2012 |
Brown NR, Seker V, Revankar ST, Downar TJ. An endothermic chemical process facility coupled to a high temperature reactor. Part I: Proposed accident scenarios within the chemical plant Nuclear Engineering and Design. 246: 256-265. DOI: 10.1016/J.Nucengdes.2011.12.027 |
0.696 |
|
2012 |
Ward AM, Seker V, Xu Y, Downar TJ. A Newton-Krylov solution to the porous medium equations in the agree code International Conference On the Physics of Reactors 2012, Physor 2012: Advances in Reactor Physics. 3: 2241-2252. |
0.677 |
|
2011 |
Kozlowski T, Xu Y, Downar TJ, Lee D. Cell homogenization method for pin-by-pin neutron transport calculations Nuclear Science and Engineering. 169: 1-18. DOI: 10.13182/Nse08-85 |
0.68 |
|
2011 |
Ward AM, Collins BS, Madariaga M, Xu Y, Downar TJ. Methods and model development for coupled RELAP5/PARCS analysis of the Atucha-II nuclear power plant Science and Technology of Nuclear Installations. 2011. DOI: 10.1155/2011/759847 |
0.588 |
|
2011 |
Gao Z, Xu Y, Downar TJ. The treatment of resonance interference effects in the subgroup method Annals of Nuclear Energy. 38: 995-1003. DOI: 10.1016/J.Anucene.2011.01.019 |
0.503 |
|
2011 |
Ortensi J, Pope MA, Strydom G, Sen RS, Dehart MD, Gougar HD, Ellis C, Baxter A, Seker V, Downar TJ, Vierow K, Ivanov K. Prismatic core coupled transient benchmark Transactions of the American Nuclear Society. 104: 854-856. |
0.669 |
|
2010 |
Brown NR, Revankar ST, Seker V, Downar TJ. Proposed chemical plant initiated accident scenarios in a sulphur-iodine cycle plant coupled to a pebble bed modular reactor Nuclear Science. 377-386. DOI: 10.1787/9789264087156-43-En |
0.694 |
|
2010 |
Brown NR, Seker V, Oh S, Revankar ST, Downar TJ, Kane C. Transient modelling of sulphur-iodine cycle thermochemical hydrogen generation coupled to pebble bed modular reactor Nuclear Science. 363-376. DOI: 10.1787/9789264087156-42-En |
0.704 |
|
2010 |
Zak T, Clarke SD, Bourne MM, Pozzi SA, Xu Y, Downar TJ, Peerani P. Neutron spectroscopy of plutonium oxide using matrix unfolding approach Nuclear Instruments and Methods in Physics Research, Section a: Accelerators, Spectrometers, Detectors and Associated Equipment. 622: 191-195. DOI: 10.1016/J.Nima.2010.07.029 |
0.62 |
|
2010 |
Ward AM, Seker V, Collins BS, Downar TJ. Thorium fuel utilization in the BWR: Lattice physics analysis of reactivity coefficients Transactions of the American Nuclear Society. 103: 821-823. |
0.662 |
|
2009 |
Xu Y, Downar T, Walls R, Ivanov K, Staudenmeier J, March-Lueba J. Application of TRACE/PARCS to BWR stability analysis Annals of Nuclear Energy. 36: 317-323. DOI: 10.1016/J.Anucene.2008.12.022 |
0.324 |
|
2009 |
Clarke SD, Pozzi SA, Flaska M, Downar TJ. Monte Carlo study of photoneutron production in U-235 following perturbations in cross section data Annals of Nuclear Energy. 36: 393-398. DOI: 10.1016/J.Anucene.2008.11.023 |
0.474 |
|
2008 |
Clarke SD, Pozzi SA, Downar TJ. Sensitivity of photoneutron production to perturbations in cross-section data International Conference On the Physics of Reactors 2008, Physor 08. 4: 3161-3168. DOI: 10.13182/Nse160-370 |
0.525 |
|
2008 |
Zhong Z, Downar TJ, Xu Y, DeHart MD, Clarno KT. Implementation of two-level coarse-mesh finite difference acceleration in an arbitrary geometry, two-dimensional discrete ordinates transport method Nuclear Science and Engineering. 158: 289-298. DOI: 10.13182/Nse06-24Tn |
0.577 |
|
2008 |
Seker V, Downar TJ. Analysis of OECD/NEA/NSC PBMR400 transient benchmark problem with PARCS International Conference On the Physics of Reactors 2008, Physor 08. 3: 1919-1926. |
0.674 |
|
2008 |
Hursin M, Downar TJ, Thomas J. PWR control rod ejection analysis with the method of characteristic code DeCART International Conference On the Physics of Reactors 2008, Physor 08. 3: 1833-1840. |
0.313 |
|
2008 |
Clarke SD, Pozzi SA, Downar TJ. Sensitivity of photoneutron production to perturbations in cross-section data International Conference On the Physics of Reactors 2008, Physor 08. 4: 3161-3168. |
0.47 |
|
2007 |
McDeavitt SM, Xu Y, Downar TJ, Solomon AA. Zirconium matrix cermet for a mixed uranium-thorium oxide fuel in an SBWR Nuclear Technology. 157: 37-52. DOI: 10.13182/Nt07-A3800 |
0.318 |
|
2007 |
Weber DP, Sofu T, Won SY, Downar TJ, Thomas JW, Zhong Z, Cho JY, Kim KS, Chun TH, Joo HG, Kim CH. High-fidelity light water reactor analysis with the numerical nuclear reactor Nuclear Science and Engineering. 155: 395-408. DOI: 10.13182/Nse07-A2672 |
0.701 |
|
2007 |
Lee HC, Noh JM, Joo HK, Lee D, Downar TJ. Fourier convergence analysis of two-dimensional/one-dimensional coupling methods for the three-dimensional neutron diffusion eigenvalue problems Nuclear Science and Engineering. 156: 74-85. DOI: 10.13182/Nse06-32 |
0.447 |
|
2007 |
Seker V, Glass C, Kramer K, Downar TJ. Monte carlo depletion analysis of a TRU burning sodium cooled fast reactor Transactions of the American Nuclear Society. 97: 846-848. |
0.683 |
|
2007 |
Seker V, Thomas JW, Downar TJ. Reactor simulation with coupled Monte Carlo and computational fluid dynamics Joint International Topical Meeting On Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + Sna 2007. |
0.679 |
|
2007 |
Seker V, Thomas JW, Downar TJ. Reactor physics simulations with coupled Monte Carlo calculation and computational fluid dynamics 13th International Conference On Emerging Nuclear Energy Systems 2007, Icenes 2007. 1: 345-349. |
0.683 |
|
2007 |
Brown NR, Seker V, Revankar ST, Downar TJ. Coupling of purdue hydrogen production cycle models to thermix American Nuclear Society Embedded Topical Meeting - 2007 International Topical Meeting On Safety and Technology of Nuclear Hydrogen Production, Control, and Management. 339-346. |
0.662 |
|
2007 |
Seker V, Downar TJ. Three-dimensional heat transfer and fluid flow for pebble bed reactor applications Transactions of the American Nuclear Society. 96: 605-606. |
0.657 |
|
2007 |
Seker V, Downar TJ. Multiphysics methods development for high temperature gas cooled reactor analysis 13th International Conference On Emerging Nuclear Energy Systems 2007, Icenes 2007. 2: 1090-1095. |
0.726 |
|
2006 |
Reitsma F, Strydom G, De Haas JBM, Ivanov K, Tyobeka B, Mphahlele R, Downar TJ, Seker V, Gougar HD, Da Cruz DF, Sikik UE. The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems Nuclear Engineering and Design. 236: 657-668. DOI: 10.1016/J.Nucengdes.2005.12.007 |
0.714 |
|
2006 |
Seker V, Downar TJ. The analysis of the OECD/NEA/NSC PBMR-400 benchmark problem using PARCS-DIREKT Physor-2006 - American Nuclear Society's Topical Meeting On Reactor Physics. 2006. |
0.699 |
|
2005 |
Todosow M, Galperin A, Herring S, Kazimi M, Downar T, Morozov A. Use of Thorium in Light Water Reactors Nuclear Technology. 151: 168-176. DOI: 10.13182/Nt151-168 |
0.32 |
|
2005 |
Zhong Z, Downar TJ, DeHart MD, Williams ML. Continuous-Energy Multidimensional S N Transport for Problem-Dependent Resonance Self-Shielding Calculations Transactions of the American Nuclear Society. 92: 754-759. DOI: 10.13182/Nse06-3 |
0.589 |
|
2005 |
Lee HC, Lee D, Downar TJ. Iterative two- and one-dimensional methods for three-dimensional neutron diffusion calculations Nuclear Science and Engineering. 151: 46-54. DOI: 10.13182/Nse04-68 |
0.442 |
|
2005 |
Seker V, Downar TJ. Analysis of a PBMR-400 control rod ejection accident using PARCS-THERMIX and the Nordheim Fuchs model Transactions of the American Nuclear Society. 93: 936-938. |
0.654 |
|
2005 |
Seker V, Downar TJ. Analysis of the OECD/NEA PBMR-268 transient benchmark problem with the PARCS neutronics code Transactions of the American Nuclear Society. 92: 697-699. |
0.682 |
|
2004 |
Kozlowski T, Miller RM, Downar TJ, Barber DA, Joo HG. Consistent Comparison of the Codes RELAP5/PARCS and TRAC-M/PARCS for the OECD MSLB Coupled Code Benchmark Nuclear Technology. 146: 15-28. DOI: 10.13182/Nt04-A3483 |
0.59 |
|
2004 |
Rohatgi US, Jo JH, Chung BD, Takahashi H, Downar TJ. Steam line break and station blackout transients for proliferation-resistant hexagonal tight lattice boiling water reactor Nuclear Technology. 145: 18-27. DOI: 10.13182/Nt04-A3457 |
0.348 |
|
2004 |
Lee D, Downar TJ, Ulses A, Akdeniz B, Ivanov KN. Analysis of the OECD/NRC BWR turbine trip transient benchmark with the coupled thermal-hydraulics and neutronics code TRAC-M/PARCS Nuclear Science and Engineering. 148: 291-305. DOI: 10.13182/Nse04-A2459 |
0.516 |
|
2004 |
Lee D, Downar TJ, Kim Y. A Nodal and Finite Difference Hybrid Method for Pin-by-Pin Heterogeneous Three-Dimensional Light Water Reactor Diffusion Calculations Nuclear Science and Engineering. 146: 319-339. DOI: 10.13182/Nse04-A2412 |
0.475 |
|
2004 |
Lee CH, Downar TJ. A hybrid nodal diffusion/SP3 method using one-node coarse-mesh finite difference formulation Nuclear Science and Engineering. 146: 176-187. DOI: 10.13182/Nse04-A2401 |
0.3 |
|
2004 |
Lee D, Downar TJ, Kim Y. Convergence analysis of the nonlinear coarse-mesh finite difference method for one-dimensional fixed-source neutron diffusion problem Nuclear Science and Engineering. 147: 127-147. DOI: 10.13182/Nse03-64 |
0.425 |
|
2004 |
Weber DP, Sofu T, Yang WS, Downar TJ, Thomas JW, Zhong Z, Joo HG. Coupled calculations using the numerical nuclear reactor for integrated simulation of neutronic and thermal-hydraulic phenomena Proceedings of the Physor 2004: the Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 69-78. |
0.311 |
|
2003 |
Tinkler DR, Downar TJ. The neutronics design and analysis of a 200-MW(electric) simplified boiling water reactor core Nuclear Technology. 142: 230-242. DOI: 10.13182/Nt02-47 |
0.355 |
|
2002 |
Kim TK, Downar TJ. Thorium fuel performance in a tight-pitch light water reactor lattice Nuclear Technology. 138: 17-29. DOI: 10.13182/Nt02-A3274 |
0.345 |
|
2001 |
Downar TJ, Joo HG. A preconditioned Krylov method for solution of the multi-dimensional, two fluid hydrodynamics equations Annals of Nuclear Energy. 28: 1251-1267. DOI: 10.1016/S0306-4549(00)00124-9 |
0.359 |
|
1999 |
Choi H, Downar TJ. Liquid-metal reactor for burning minor actinides of spent light water reactor fuel - II: nuclear data uncertainty analysis Nuclear Science and Engineering. 133: 23-39. DOI: 10.13182/Nse99-A2070 |
0.339 |
|
1999 |
Choi H, Downar TJ. Liquid-metal reactor for burning minor actinides of spent light water reactor fuel - I: neutronics design study Nuclear Science and Engineering. 133: 1-22. DOI: 10.13182/Nse99-A2069 |
0.308 |
|
1998 |
Gose GC, Downar TJ, Ott KO. Analysis of the reactivity during a pressurized water reactor main-steam-line-break transient Nuclear Technology. 124: 284-289. DOI: 10.13182/Nt98-A2927 |
0.307 |
|
1998 |
Joo HG, Jiang G, Downar TJ. Stabilization techniques for the nonlinear analytic nodal method Nuclear Science and Engineering. 130: 47-59. DOI: 10.13182/Nse98-A1988 |
0.546 |
|
1998 |
Janardhan R, Downar T. A Nested FGMRES Method for Parallel Calculation of Nuclear Reactor Transients Journal of Scientific Computing. 13: 65-93. DOI: 10.1023/A:1023256711255 |
0.379 |
|
1997 |
Downar TJ, Wu JY, Steill J, Janardhan R. Parallel and serial applications of the RETRAN-03 power plant simulation code using domain decomposition and Krylov subspace methods Nuclear Technology. 117: 133-150. DOI: 10.13182/Nt97-A35320 |
0.37 |
|
1996 |
Joo HG, Downar TJ. An incomplete domain decomposition preconditioning method for nonlinear nodal kinetics calculations Nuclear Science and Engineering. 123: 403-414. DOI: 10.13182/Nse96-A24203 |
0.336 |
|
1995 |
Stevens JG, Smith KS, Rempe KR, Downar TJ. Optimization of pressurized water reactor shuffling by simulated annealing with heuristics Nuclear Science and Engineering. 121: 67-88. DOI: 10.13182/Nse121-67 |
0.311 |
|
1995 |
Downar TJ, Phegley DA. Harmonic perturbation theory for the analysis of boiling water reactor regional instabilities Annals of Nuclear Energy. 22: 339-357. DOI: 10.1016/0306-4549(94)00066-N |
0.32 |
|
1993 |
Downar TJ. Depletion perturbation theory within the framework of an advanced hexagonal nodal method Nuclear Science and Engineering. 115: 334-340. DOI: 10.13182/Nse93-A24063 |
0.346 |
|
1993 |
Zika MR, Downar TJ. Numerical divergence effects of equivalence theory in the nodal expansion method Nuclear Science and Engineering. 115: 219-232. DOI: 10.13182/Nse93-A24051 |
0.37 |
|
1992 |
Choi HB, Downar TJ. Sensitivity theory for the closed nuclear fuel cycle Nuclear Science and Engineering. 111: 205-213. DOI: 10.13182/Nse92-A23934 |
0.337 |
|
1992 |
Downar TJ. Depletion perturbation theory for burnup dependent microscopic cross sections Annals of Nuclear Energy. 19: 27-37. DOI: 10.1016/0306-4549(92)90051-C |
0.325 |
|
1991 |
Downar TJ, Khalil H. Uncertainty in the burnup reactivity swing of liquid-metal fast reactors Nuclear Science and Engineering. 109: 278-296. DOI: 10.13182/Nse91-A23853 |
0.308 |
|
1990 |
Yang WS, Downar TJ. A linear time-dependent flux approximation for nuclide depletion based on a perturbation method Annals of Nuclear Energy. 17: 37-42. DOI: 10.1016/0306-4549(90)90063-J |
0.332 |
|
1989 |
Yang WS, Downar TJ. Depletion perturbation theory for the constrained equilibrium cycle Nuclear Science and Engineering. 102: 365-380. DOI: 10.13182/Nse89-A23648 |
0.329 |
|
1988 |
Yang WS, Downar TJ. Generalized perturbation theory for constant power core depletion Nuclear Science and Engineering. 99: 353-366. DOI: 10.13182/Nse99-353 |
0.337 |
|
1988 |
Wemple CA, Dilber I, Downar TJ. Vectorized Source Algorithm For The Light Water Reactor Coarse-Mesh Nodal Code Simulate-E. Nuclear Science and Engineering. 99: 36-40. DOI: 10.13182/Nse88-A23543 |
0.332 |
|
1988 |
Hwang HR, Downar TJ. Optimal space-time fuel distribution in a 1-D numerical core model Annals of Nuclear Energy. 15: 219-234. DOI: 10.1016/0306-4549(88)90112-0 |
0.341 |
|
1987 |
Downar TJ. Moderator feedback effects in two-dimensional nodal methods for pressurized water reactor analysis Nuclear Technology. 76: 303-307. DOI: 10.13182/Nt87-A33883 |
0.35 |
|
1987 |
Kim YJ, Downar TJ, Sesonske A. Optimization Of Core Reload Design For Low-Leakage Fuel Management In Pressurized Water Reactors Nuclear Science and Engineering. 96: 85-101. DOI: 10.13182/Nse87-A16369 |
0.314 |
|
1987 |
Downar TJ. Reactivity space analysis of PWR core depletion Annals of Nuclear Energy. 14: 135-144. DOI: 10.1016/0306-4549(87)90087-9 |
0.361 |
|
1986 |
Downar TJ, Stillman JA. EXPLICIT BURNABLE ABSORBER MODELING FOR PRESSURIZED WATER REACTOR CORE RELOAD DESIGN APPLICATIONS Nuclear Science and Engineering. 94: 241-250. DOI: 10.13182/Nse86-A17267 |
0.332 |
|
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