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John White

John White
John R WhiteProfessor
  • CollegeFrancis College of Engineering
  • DepartmentChemical Engineering
  • Phone(978) 934-3165
  • EmailJohn_White@uml.edu

Research Interests

Nuclear reactor physics methods development and applications; design and optimization of LWR reload cores using generalized perturbation theory methods; computer methods and PC applications of reactor analysis tools.

Education

  • Other: Introduction to InduSoft Web Studio, (2003), InduSoft Web Studio - Austin, TX
  • Other: Fluent/Gambit Training Course, (1999), Fluent Inc. - Lebanon, NH
  • Other: Effective Teaching: A Workshop, (1996), -
  • Other: Condition Assessment of Nuclear Reactor Pressure Vessel Steel, (1993), ASTM Standards Technology Training - Vail, CO
  • Other: Artificial Intelligence, (1987), ANS Tutorial Workshop - Snowbird, UT
  • Ph D: Nuclear Engineering, (1987), University of Tennessee - Knoxville, TN
  • Other: Dynamic Simulation of Nuclear Power Plants, (1984), ANL Faculty Workshop - Argonne National Laboratory, Argonne, IL
  • Other: Trends in Nuclear Engineering Computing, (1984), ANL Faculty/Student Workshop - Argonne, IL
  • Other: Fusion Plasma Engineering, (1984), ANS Short Course - New Orleans, LA
  • Other: Basic Mechanical Design, (1983), Computervision Training - University of Lowell, Lowell, MA
  • Other: Advances in Nuclear Systems Thermal Analysis, (1983), MIT Short Course - Massachusetts Institute of Technology
  • Other: Thermal-Hydraulic Design and Safety for Light Water Reactors, (1983), MIT Short Course - Massachusetts Institute of Technology
  • MS: Nuclear Engineering, (1980), University of Tennessee - Knoxville, TN
  • BS: Nuclear Engineering, (1977), University of Lowell - Lowell, MA

Publications

  • White, J.R. (2014) "Reactor laboratory modules available at the UMass-Lowell research reactor," American Nuclear Society 111: pp. 165-168
  • Salawu, A., White, J.R., Balogun, G., Jonah, S., Zakari, Y., others, . (2013) "Designing a 2D RZ Venture Model for Neutronic Analysis of the Nigeria Research Reactor-1 (NIRR-1)," Advances in Physics Theories and Applications 23: pp. 26–30
  • Pennell, S., Avitabile, P., White, J.R. (2009) "An engineering-oriented approach to the introductory differential equations course," PRIMUS 19:1 pp. 88-99
  • Bousbia-Salah, A., Jirapongmed, A., Hamidouche, T., White, J.R., D’Auria, F., Adorni, M. (2006) "Assessment of RELAP5 model for the University of Massachusetts Lowell research reactor," Nuclear Technology and Radiation Protection 21:1 pp. 3–12
  • Pennell, S.A., Avitabile, P., White, J.R. (2005) "An interdisciplinary, multisemester project relating differential equations and engineering,"
  • White, J.R., BOBEK, L. (2005) "HEU to LEU conversion experience at the UMass-Lowell research reactor," Research Reactor Fuel Management pp. 149
  • White, J.R., Kinsmen, D., Regan, T.M., Bobek, L.M. (2005) "Novel Nuclear Powered Photocatalytic Energy Conversion," University of Massachusetts Lowell
  • Regan, T.M., Harris, D.C., Stroud, R.M., White, J.R. (2002) "Neutron irradiation of sapphire for compressive strengthening. - I. Processing conditions and compressive strength," Journal of Nuclear Materials 300:1 pp. 39-46
  • Byard, J., White, J.R. (2001) "Information retrieval system for the life of the LEU-fueled UMass-Lowell research reactor,"
  • Bhutta, M.B., White, J.R. (1995) "Modeling of various nuclear systems using the Monte Carlo code MCNP,"
  • White, J.R., Spinney, K.B., Morrissey, K.J., Cacciapouti, R.J. (1994) "Comparison of the BUGLE-80 and SAILOR libraries for coupled neutron-gamma transport applications," ASTM Special Technical Publication STP 1228: pp. 650-9
  • White, J.R., Spinney, K.B., Morrissey, K.J., Cacciapouti, R.J. (1994) "Maine Yankee dosimetry capsule and pressure vessel neutron fluence calculations," ASTM Special Technical Publication STP 1228: pp. 114-22
  • Kumar, A., White, J.R. (1994) "Preliminary investigation of neutron filtering effects for application in boron neutron capture therapy,"
  • White, J.R., Delorey, T.F. (1991) "Sensitivity and Uncertainty Analysis of Integral Physics Parameters in High-Conversion Reactor Systems," Nuclear Technology 95:2
  • White, J.R., Swanbon, G.A. (1990) "Development of a technique for the practical implementation of higher order perturbation methods," Nuclear Science and Engineering 105:2 pp. 160-173
  • White, J.R., Chapman, D.M., Biswas, D. (1985) "Development of a Gpt-Based Optimization Algorithm," Transactions of the American Nuclear Society 50:NOV
  • Frank, B.R., White, J.R. (1985) "Evaluation of the Dif3d Nodal Option for Htgr Neutronic Applications," Transactions of the American Nuclear Society 49:JUN
  • White, J.R., Cahill, T.J., Frank, B.R. (1985) "Exact Analytic Solution for the Generalized Flux in One-Dimensional Cartesian Geometry," Transactions of the American Nuclear Society 49:JUN
  • White, J.R., Konovalchick, J., Marable, J.H., Lucius, J.L. (1983) "Sensitivity Analysis of the Doppler Coefficient in Heterogeneous Lmfbrs," Transactions of the American Nuclear Society 45:

Presentations

  • Innovative Use of a Research Reactor for Interdisciplinary Engineering Education - ASEE Conference, June 2007 - Honolulu, HI
  • Reactor Operations Training via Web-Based Access to the UMass-Lowell Research Reactor - Conference on Nuclear Training and Education, February 2007 - Jacksonville, FL
  • HEU to LEU Conversion Experience at the UMass-Lowell Research Reactor - 9th International Topical Meeting on Research Reactor Fuel Management, April 2005 - Budapest, Hungary
  • A Web-Based System for Access to Real-Time and Archival Research Reactor Data, April 2005 - University of Pisa, Italy
  • A Web-Based System for Access to Real-Time and Archival Research Reactor Data - ANS 2004 Annual Meeting, June 2004 - Pittsburgh, PA
  • Startup Test Results and Model Evaluation for the HEU to LEU Conversion of the UMass-Lowell Research Reactor - 24th International Meeting on Reduced Enrichment for Research and Test Reactors, November 2002 - San Carlos de Bariloche, Argentina
  • Design and Initial Testing of an Ex-Core Fast Neutron Irradiator for the UMass-Lowell Research Reactor - Radiation Protection and Shielding Division Topical Meeting, April 2002 - Santa Fe, NM
  • Calculational Support for the Startup of the LEU -Fueled UMass-Lowell Research Reactor - Topical Meeting on Advances in Reactor Physics and Mathematics and Computation, May 2000 - Pittsburgh, PA
  • Preliminary Characterization of the Irradiation Facilities Within the LEU-Fueled UMass-Lowell Research Reactor - Topical Meeting on Advances in Reactor Physics and Mathematics and Computation, May 2000 - Pittsburgh, PA
  • Modeling and Reference Core Calculations for the LEU-Fueled UMass-Lowell Research Reactor - ANS 1999 Winter Meeting, November 1999 - Long Beach, CA
  • Computer Modeling for Particle Transport and Shielding Applications - An Overview - Health Physics Seminar, February 1999 - UMass-Lowell, Lowell, MA
  • Updated Results for the JPDR Activation Analysis Benchmark Using VITAMIN-B6 and BUGLE-96 Data - 1998 ANS Radiation Protection and Shielding Topical Conference, April 1998 - Nashville, TN
  • Using Computer Technology in the Traditional Classroom Environment - UMass Instructional Technology Conference, April 1997 - Boxborough, MA
  • UMass-Lowell Results for the JPDR Activation Analysis Benchmark - ANS/ENS International Meeting, November 1996 - Washington, D.C.
  • Determination of the Service Life for the Excore Neutron Detector Cables in Seabrook Station - 1996 Radiation Protection & Shielding Topical Meeting, April 1996 - No. Farmouth, MA
  • UMass-Lowell Results for the JPDR Activation Analysis Benchmark - 1996 Radiation Protection & Shielding Topical Meeting, April 1996 - No. Farmouth. MA
  • Evaluation of Excore Detector Cable Service Life at Seabrook Station - Energy Engineering Seminar, February 1996 - UMass-Lowell, Lowell, MA
  • Preliminary UMass-Lowell Results of the IAEA Benchmark Calculation of Radioactive Inventory for Fission Reactor Decommissioning - Consultant's Meeting at International Atomic Energy Agency Headquarters, December 1994 - Vienna, Austria
  • Perturbation Theory to the Rescue - An Overview of Generalized Perturbation Theory Methods for a Variety of Core Physics Applications - Knolls Atomic Power Laboratory, October 1994 - Schenectady, New York
  • Comparison of the BUGLE-80 and SAILOR Libraries for Coupled Neutron-Gamma Transport Applications - Eighth ASTM-EURATOM Symposium on Reactor Dosimetry, August 1993 - Vail, CO
  • Maine Yankee Dosimetry Capsule and Pressure Vessel Neutron Fluence Calculations - Eighth ASTM-EURATOM Symposium on Reactor Dosimetry, August 1993 - Vail, CO
  • LWR Core Design and Analysis Using the RESCUE Interactive Reload Design Tool - AI 91: Frontiers in Innovative Computing for the Nuclear Industry, September 1991 - Jackson. WY
  • Integrating Computer Literacy into the Nuclear Engineering Curriculum - ASEE Annual Conference, June 1991 - New Orleans, LO
  • Implicit Versus Explicit Perturbation Methods for the Efficient Evaluation of Alternative Core Designs - International Topical Meeting on Advances in Mathematics, Computations, and Reactor Physics, April 1991 - Pittsburgh, PA
  • RESCUE _ A PC-Based Interactive Reload Design Tool - ANS 1990 Winter Meeting, November 1990 - Washington, D.C.
  • An Implicit High-Order GPT Method for LWR Reload Design Applications - ANS 1990 Annual Meeting, June 1990 - Nashville, TN
  • Accurate LWR Assembly Power Distributions Based on Generalized Perturbation Theory - International Conference on the Physics of Reactors: Operation, Design, and Computation, April 1990 - Marseille, France
  • Data Uncertainty Reduction in High Converter Reactor Designs Using PROTEUS Phase II Integral Experiments - International Conference on the Physics of Reactors: Operation, Design, and Computation, April 1990 - Marseille, France
  • Developing Feasible Loading Patterns Using Perturbation Theory Methods - International Conference on the Physics of Reactors: Operation, Design, and Computation, April 1990 - Marseille, France
  • A Practical Approach to Higher-Order Generalized Perturbation Theory - ANS Topical Meeting on Advances in Nuclear Engineering Computation and Radiation Shielding, April 1989 - Santa Fe, NM
  • Physics Analyses for the HEU to LEU Conversion at the University of Lowell Research Reactor - 1988 International Reactor Physics Conference, September 1988 - Jackson Hole, WY
  • An Overview of Two Perturbation Theory Applications, July 1988 - Wurenlingen, Switzerland
  • Verification of the Computational Models for the Physics Analysis of the University of Lowell Reactor - ANS Annual Meeting, June 1988 - San Diego, CA
  • Physics Modeling of the University of Lowell Reactor - Reduced Enrichment for Research and Test Reactors (RERTR) Meeting, July 1987 - Argonne National Laboratory
  • Analytic Solutions to Several Forms of the One-Dimensional Multigroup Diffusion Equation - International Topical Meeting on Advances in Reactor Physics Mathematics and Computations, April 1987 - Paris, France
  • Conceptual Development of a Complete LWR Reload Design Methodology Based on Generalized Perturbation Theory, October 1986 - Knoxville, TN
  • Generalized Perturbation Theory for LWR Depletion Analysis and Core Design Applications - ANS Topical Meeting on Advances in Reactor Physics and Safety, September 1986 - Saratoga Springs, NY
  • Numerical Optimization Methods in Nuclear Fear Management - SIAM 1986 National Meeting, July 1986 - Boston, MA
  • Static Generalized Perturbation Theory with Feedback Effects and Criticality Reset - ANS Annual Meeting, June 1986 - Reno, NV
  • Fuel Management Optimization Based on Generalized Perturbation Theory - ANS Topical Meeting on Advances in Fuel Management, March 1986 - Pinehurst, NC
  • Development of a GPT-Based Optimization Algorithm - ANS Winter Meeting, November 1985 - San Francisco, CA
  • Exact Analytic Solution for the Generalized Flux in 1-D Cartesian Geometry - ANS Annual Meeting, June 1985 - Boston, MA
  • Analytic Solution for the Fundamental and Higher Harmonics of the 1-D Diffusion Equation - ANS Annual Meeting, June 1984 - New Orleans, LA
  • An Overview of Static and Time-Dependent Generalized Perturbation Theory Methods and Their Potential Applications in LWR Physics Analyses, December 1983 - Pittsburgh, PA
  • Sensitivity Analysis of the Doppler Coefficient in Heterogeneous LMFBRs - ANS Winter Meeting, November 1983 - San Francisco, CA
  • An Overview of Sensitivity Analysis Methods and Their Application to the Evaluation of Design Uncertainties, March 1983 - Lowell, MA
  • An Overview of Depletion Perturbation Theory with Potential Application to the Analysis of FFTF Burnup Data - Annual LCCEWG Meeting, March 1983
  • ORNL Results for the Large Core Code Evaluation Working Group (LCCEWG), Benchmark Problem IV - Annual LCCEWG Meeting, March 1983
  • Sensitivity Analysis of the Inherent Neutron Source Strength - ANS Winter Meeting, November 1982 - Washington, D.C.
  • Application of Time-Dependent Generalized Perturbation Theory Methods in LWR Physics Analysis - ANS Topical Meeting on Reactor Physics and Core Thermal Hydraulics, September 1982 - Kiamesha Lake, NY
  • Analysis of the Lumped Fission Product Uncertainty in CRBR - ANS Winter Meeting, November 1981 - San Francisco, CA
  • Methods Development and Sensitivity and Uncertainty Analysis Capabilities: An Overview Emphasizing the Recent Evaluation of the Fission Product Worth Uncertainty in CRBR - Breeder Reactor Base Technology Program Information Meeting, September 1981
  • Analysis of the Lumped Fission Product Uncertainty in CRBR - Sensitivity and Uncertainty Analysis Users' Group Specialists Meeting, September 1981
  • Potential Use of Sensitivity-Based Methods as a Reactor Design and Optimization Tool - Sensitivity and Uncertainty Analysis Users' Group Specialists Meeting, September 1981
  • Sensitivity Theory for Reactor Analysis and Its Application in the Design of Fast Breeder Reactors - Union Carbide Nuclear Division Information Meeting, September 1981
  • Burnup Effects in Data Sensitivity Studies - ANS Winter Meeting, November 1980 - Washington, DC
  • On the Implementation, Verification, and Application of Multicycle Depletion Perturbation Theory - ANS Topical Meeting on Advances in Reactor Physics and Shielding, September 1980 - Sun Valley, ID
  • Analysis of the Thorium Axial Blanket Experiments in the PROTEUS Reactor - ANS Annual Meeting, June 1980 - Las Vegas, NV
  • Development and Verification of Multicycle Depletion Perturbation Theory - ANS Annual Meeting, June 1980 - Las Vegas, NV
  • Analysis of the EIR-PROTEUS Thorium-Based Experiments - GCFR Annual Information Meeting, May 1980
  • Analysis of a Swiss Thorium Blanket Integral Experiment - International Conference on Nuclear Cross Sections for Technology, October 1979 - Knoxville, TN
  • Alternative Heterogeneous GCFR Fuel Cycles - ANS Annual Meeting, June 1979 - Atlanta, GA
  • Reactor Physics of Alternate GCFR Concepts - GCFR Annual Information Meeting, May 1979

Contracts, Fellowships, Grants and Sponsored Research

  • UMass-Lowell Nuclear Engineering and Radiological Science Scholarship Program (2013), Grant -
    White, J.R. (Co-Principal)
  • UMass-Lowell Nuclear Engineering and Radiological Science Scholarship Program (2013), Grant -
    White, J.R. (Co-Principal)
  • Nuclear Engineering Education and Training (NEET) Summer Institute (2013), -
    White, J.R. (Co-Principal)
  • Nuclear Engineering Education and Training (NEET) Summer Institute (2013), -
    White, J.R. (Co-Principal)
  • Development of Reactor Experiments Course at UMass-Lowell (2011), Grant -
    White, J.R. (Principal)
  • MCNP Modeling of the UMLRR MCNP (2010), - Naval Undersea Warfare Center
    White, J.R. (Principal)