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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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