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RAE Publications -
Reactor Physics
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Publications - Reactor Physics
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List of Publications

  • Using a Wavelet Approach in the Reactor Parameter Simulation System A. Miron Ph.D. Proposal, University of Cincinnati, U.S.A., February, 2000.

  • A Wavelet Approach to the Development and Application of a Stochastic Parameter Simulation System A. Miron, Ph.D. Disseration, University of Cincinnati. www.ohiolink.edu/etd, U.S.A., August, 2001.

  • Copyright/Patent for the Stochastic Parameter Simulation System (SPSS) ver. 1.0 A. Miron, J. Christenson University of Cincinnati, U.S.A., Ocotober, 2001 (pending).

  • Neutron Multiplier Designs for the Accelerator-Driven Test Facility SCM-100 L. Mercatali, J. A. Stillman, T. A. Taiwo, G. Palmiotti, R. N. Hill, J. Roglans Trans. Am. Nucl. Soc., 86, 357 (2002).

  • OECD/NEA PWR MSLB Benchmark Sensitivity Studies Using SAS-DIF3DK T. A. Taiwo, F. E. Dunn, J. E. Cahalan, H. S. Khalil Proc. of the International Conference on Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, Spain, September, 1999, Vol. 1, pp. 333 (1999).

  • Space-Angle Approximations in the Variational Nodal Method E. E. Lewis, G. Palmiotti, T. A. Taiwo Proc. of the International Conference on Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, Spain, September, 1999, Vol. 1, pp. 827 (1999).

  • Coupled Reactor Physics and Coolant Dynamics of Heavy Liquid Metal Coolant Systems J. E. Cahalan, F. E. Dunn, and T. A. Taiwo Trans. Am. Nucl. Soc., 81, (1999).

  • Whole-Core Neutron Transport Calculations Without Cross Section Homogenization M. A. Smith, N. Tsoulfanidis, E. E. Lewis, G. Palmiotti, T. A. Taiwo ICONE-8; Eighth International Conference on Nuclear Engineering, Baltimore, Maryland, U.S.A, April, 2000.

  • Development of a Coupled Dynamics Code with Transport Theory Capability and Application to Accelerator-Driven Systems Transients J. E. Cahalan, T. Ama, G. Palmiotti, T. A. Taiwo, and W. S. Yang, Proc. of ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, PHYSOR 2000, Pittsburgh, Pennsylvania, U.S.A., May, 2000.

  • Whole-Core Neutron Transport Calculations Without Fuel-Coolant Homogenization M. A. Smith, N. Tsoulfanidis, E. E. Lewis, G. Palmiotti, T. A. Taiwo Proc. of ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, PHYSOR 2000, Pittsburgh, Pennsylvania, U.S.A., May, 2000.

  • Verification of Physics Predictions for GT/AD-MHR Core Designs Y. Gohar, T. A. Taiwo, C. G. Stenberg, P. J. Finck Trans. Am. Nucl. Soc., 83, (2000).

  • Numerical Optimization of Computing Algorithms of the Variational Nodal Method W. S. Yang, G. Palmiotti, and E. E. Lewis PHYSOR 2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, Pittsburgh, Pennsylvania, May 7-11, 2000.

  • Development of a Coupled Dynamics Code with Transport Theory Capability J. E. Cahalan, T. Ama, G. Palmiotti, T. A. Taiwo, and W. S. Yang PHYSOR 2000 ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium, Pittsburgh, Pennsylvania, May 7-11, 2000.

  • Numerical Optimization of Computing Algorithms of the Variational Nodal Method Based on Transformations of Variables W. S. Yang, G. Palmiotti, and E. E. Lewis Nucl. Sci. and Eng., 139, 174 (2001).

  • Advances in ANL Reactor Physics Methods Inspired by A. F. Henry H. S. Khalil, T. A. Taiwo, W. S. Yang, and P. J. Finck Trans. Am. Nucl. Soc., 85, 283 (2001).

  • Monte Carlo Source Convergence and the Whitesides Problem R. N. Blomquist Proceedings of the ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation to the Next Millenium, Pittsburgh, PA, May 7-12, 2000. (CD-ROM)

  • VIM: A Continuous Energy Monte Carlo Criticality Code R. N. Blomquist Proceedings of the ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millenium, Pittsburgh, PA, May 7-12, 2000. (CD-ROM)

  • Status of the VIM Monte Carlo Neutron/Photon Transport Code R. N. Blomquist Proceedings of the 12th Biennial RPSD Topical Meeting, Santa Fe, NM, April 14-18, 2002. (CD-ROM)

  • Alternative Implementations of the Monte Carlo Power Method R. N. Blomquist and E. M. Gelbard ANL-01/15, December, 2001.

  • Alternative Implementations of the Monte Carlo Power Method R. N. Blomquist and E. M. Gelbard Nucl. Sci. Eng. 141, pp 85-100 (2002).

  • Fission Source Algorithms and Monte Carlo Variances R. N. Blomquist and E. M. Gelbard ANS Transactions 84, pp 172-173, June, 2001.

  • Status of the VIM Monte Carlo Neutron/Photon Transport Code R. N. Blomquist Proceedings of the 12th Biennial RPSD Topical Meeting (ANS), Santa Fe, NM, April 14-18, 2002 (CD-ROM).

  • VIM Calculations of ICSBEP Pu Benchmarks for ANS-8/ANSI J. W. Thomas and R. N. Blomquist ANS Transactions 86, pp 53-55, June, 2002.

  • Interfacial Transport Phenomena and Stability in Molten Metal-Water Systems H. Kim, M. Anderson, R. Bonazza, M. Corradini and D. H. Cho Presented at ICONE-8, April 2-6, 2000, Baltimore, MD.

  • Advances in ANL Reactor Physics Methods Inspired by A. F. Henry H. S. Khalil, T. A. Taiwo, W. S. Yang, P. J. Finck Trans. Am. Nucl. Soc., 85, 283 (2001).

  • Physics Studies for a Particle-Bed Gas Cooled Fast Reactor Core Design T. Taiwo, M. Fatone, G. Palmiotti, and R. N. Hill Proceedings of the 1st International Topical Meeting on High Temperature Reactor Technology (HTR 2002), Petten, Netherlands, April 22-24, 2002.



Reactor Analysis and Engineering Division at Argonne National Laboratory - http://www.rae.anl.gov