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General Reactor Physics and Shielding Applications
Prof. John R. White

Since most of my work is somehow related to reactor physics, this is a catch-all category that includes research work not covered explicitly under the other three special topics listed on previous pages. This page simply lists a sequence of selected papers, reports, and student theses that document my involvement in the area of general reactor physics and shielding applications. Unfortunately, since most of these references are quite old, electronic versions of these documents are not available. The list here simply documents additional personal areas of interest and expertise.

Fast Breeder Reactors and Alternative Fuel Cycles
T. J. Burns, J. R. White, D. E. Bartine, J. M. Kallfelz, and D. M. Rowland, "Denatured Fast Reactor Symbiosis," Trans. Am. Nuc. Soc., 27, 454 (Nov. 1977).

D. E. Bartine, T. J. Burns, J. R. White, J. M. Kallfelz, and D. M. Rowland, "Alternative Fuel Cycles for Breeder Reactors," International Conference on Alternative Energy Sources, Miami Beach, Florida (Dec. 1977).

D. E. Bartine, T. J. Burns, J. R. White, J. M. Kallfelz, and D. M. Rowland, "Alternative Fuel Cycles for Breeder Reactors," ANS Topical Meeting on Advances in Reactor Physics, Gatlinburg, Tennessee (April 1978).

T. J. Burns and J. R. White, "Preliminary Evaluation of Alternative Fuel Cycle Options Utilizing Fast Breeders," Oak Ridge National Laboratory, ORNL-5389, (Oct. 1978).

J. R. White and T. J. Burns, "Alternative Heterogeneous GCFR Fuel Cycles," Trans. Am. Nuc. Soc., 32, 403 (June 1979).

T. J. Burns and J. R. White, "Preliminary Neutronic Analysis of a Fast Mixed-Spectrum Reactor (FMSR)," Oak Ridge National Laboratory, ORNL/TM-6954 (Aug. 1979).

J. R. White, D. T. Ingersoll, U. Schmocker, and K. Gmur, "Analysis of a Swiss Thorium Blanket Integral Experiment," International Conf. on Nuclear Cross Sections for Technology, Knoxville, TN. (Oct. 1979).

J. R. White and T. J. Burns, "Analysis of Fission-Product Effects in a Fast Mixed-Spectrum Reactor Concept," Oak Ridge National Laboratory, ORNL/TM-7091 (Feb. 1980).

J. R. White, D. T. Ingersoll, U. Schmocker, and K. Gmur, "Analysis of the Thorium Axial Blanket Experiments in the PROTEUS Reactor," Trans. Am. Nuc. Soc., 34, 759 (June 1980).

J. R. White and T. J. Burns, "Preliminary Evaluation of Alternate Fueled Gas Cooled Fast Reactors," Oak Ridge National Laboratory, ORNL/TM-7432 (Dec. 1980).

J. R. White and D. T. Ingersoll, "Analysis of the Thorium Axial Blanket Experiments in the PROTEUS Reactor," Oak Ridge National Laboratory, ORNL/TM-7471 (Dec. 1980).

B. R. Frank and J. R. White, "Few-Group Three-Dimensional Hexagonal HTGR Benchmark Problem," ANS International Meeting on Advances in Nuclear Engineering Computational Methods, Knoxville, TN. (April 1985).

B. R. Frank and J. R. White, "Evaluation of the DIF3D Nodal Option for HTGR Neutronic Applications," Trans. Am. Nuc. Soc., 49 (June 1985).

Reactor Shielding and Radiation Transport Applications
K. B. Spinney, K. J. Morrissey, and J. R. White, "Equilibrium Cycle Excore Neutron and Gamma Fluxes for the GE Simplified Boiling Water Reactor," YAEC-1858, Yankee Atomic Electric Company (May 1993).

J. R. White, et al., "Maine Yankee Dosimetry Capsule and Pressure Vessel Neutron Fluence Calculations," Eighth ASTM-EURATOM Symposium on Reactor Dosimetry, Vail, Colorado (Aug. 1993).

J. R. White, et al., "Comparison of the BUGLE-80 and SAILOR Libraries for Coupled Neutron-Gamma Transport Applications," Eighth ASTM-EURATOM Symposium on Reactor Dosimetry, Vail, Colorado (Aug. 1993).

K. B. Spinney, J. R. White, and R. C. Paulson, "Determination of Neutron and Gamma Radiation Fields in a Mark I BWR Drywell via Calculation and Measurement," Proceedings of the 8th International Conference on Radiation Shielding, Arlington, Texas (April 1994).

J. R. White, "Summary Results of the MCNP-MCNP Coupling Studies for the Point Source KSU Skyshine Benchmark Problem," technical report submitted to Yankee Atomic Electric Company (Jan. 1997).

Selected Student Theses (General Reactor Physics Applications)
Frederick L. Carpenito, "Nuclear Fuel Storage Criticality Analysis Methodology," MS Thesis, Energy Engineering (Nuclear Option), University of Lowell (May 1984).

Keith B. Spinney, "A One-Dimensional Two-Group Diffusion Theory Code to Model Axial Xenon Oscillations," MS Thesis, Energy Engineering (Nuclear Option), University of Lowell (Sept. 1985).

Mark R. Durrenberger, "Design of Yankee Fuel Assemblies with Zoned Enrichments and Gadolinia Shims to Achieve Longer Fuel Cycles," MS Thesis, Energy Engineering (Nuclear Option), University of Lowell (Sept. 1988).

Eric M. Edmonds, "Benchmarking of Methods and Models Used in High Temperature Gas Cooled Reactor Design Using Data From the Dragon and Clean Critical Experiments," MS Thesis, Energy Engineering (Nuclear Option), UMass-Lowell (Oct. 1993).

Anil Kumar, "Preliminary Investigation of Neutron Filtering Effects for Application in Boron Neutron Capture Therapy," MS Thesis, Energy Engineering (Nuclear Option), UMass-Lowell (Sept. 1994).

Muhammad Bilal Bhutta, "Modeling of Various Nuclear Systems Using the Monte Carlo Code MCNP," MS Thesis, Energy Engineering (Nuclear Option), UMass-Lowell (April 1995).

Grace M. Lam, "Criticality Analysis of Spent Fuel Storage Options using KENO-Va and MCNP," MS Thesis, Energy Engineering (Nuclear Option), UMass-Lowell (Dec. 1995).

Last updated by Prof. John R. White (January 2003)

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