William S. Charlton

Associate Professor, Nuclear Engineering

Director, Nuclear Security Science and Policy Institute, Texas Engineering Experiment Station

Date of Appointment: 2003

Office: Teague Research Center Rm 322
Phone: 979/845-7092
Fax: 979/845-6443
E-mail: wcharlton@tamu.edu

Mailing Address: Texas A&M University
Department of Nuclear Engineering
3133 TAMU
College Station, TX 77843-3133

Education
Ph.D. Nuclear Engineering, Texas A&M University, 1999
M.S. Nuclear Engineering, Texas A&M University, 1997
B.S. Nuclear Engineering, Texas A&M University, 1995

Courses
NUEN 405, Nuclear Engineering Experiments
NUEN 489, Nuclear Reactor Assembly Design
NUEN 489, Nuclear Nonproliferation
NUEN 601, Nuclear Reactor Theory
NUEN 650, Nuclear Nonproliferation and Arms Control
NUEN 689, Critical Analysis of Nuclear Security Data
BUSH 689, Weapons of Mass Destruction Response and Recovery

Areas of Interest
Nuclear nonproliferation and international security: interests include reactor modeling for material production calculations, inverse problem analysis, signature development for identification of covert nuclear weapons programs, nuclear terrorism, treaty verification technique development, and innovative safeguards methodologies.

Reactor physics and fuel cycle analysis: interests include lattice and full core modeling applications, proliferation resistance modeling for fuel cycles, transmuter fuels, and development of proliferation resistant nuclear fuels.

Reactor experimentation and nuclear data development: interests include development of benchmark experiments for reactor physics code verification, development of experimental measurement techniques, and measurement and analysis of fundamental nuclear data.

Curriculum Vita

EXPERIENCE
Director, Nuclear Security Science and Policy Institute, Texas Engineering Experiment Station, 2006-present
Associate Professor, Nuclear Engineering Department, Texas A&M University, 2003-present
Assistant Professor, Nuclear and Radiation Engineering Program, Mechanical Engineering Department, University of Texas at Austin, 2000–2003
Technical Staff Member, NIS-7, Safeguards Systems Group, Los Alamos National Laboratory, 1998–2000

AWARDS/RECOMMENDATIONS
George Armistead, Jr. ’23 Faculty Fellow, Texas A&M University, 2005.
Engineering Foundation/Halliburton Young Faculty Award, University of Texas, 2001.
Best Paper Award, Reactor Physics Division, 1998 ANS Winter Meeting, Washington, D.C.
Nonproliferation and International Security Division Scholarship, LANL, 1998–1999.
Board of Regents Fellowship, TAMU, 1995–1996.

PROFESSIONAL ACTIVITIES
Los Alamos National Laboratory
Consultant for the Nonproliferation and International Security Division (2000-present)

University of Texas at Austin
Member of the University of Texas at Austin College of Engineering Honors Committee (2002-present)
Student advisor for the University of Texas Local Chapter of the American Nuclear Society (2001-present)
Member of the University of Texas at Austin Nuclear Reactor Committee (2001-present)
Member of the University of Texas at Austin Radiation Safety Committee (2001-present)
Member of the Department of Mechanical Engineering PROCEED Committee and the Thermal Fluid Systems Group PROCEED Subcommittee (2001-present)
Member of the Nuclear Engineering Teaching Laboratory Executive Committee (2000-present)

International Atomic Energy Agency
Hosted the 13th International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials (SSAC) at the Nuclear Engineering Teaching Laboratory of the University of Texas at Austin (May 14-18, 2001)

Institute for Nuclear Materials Management
Faculty advisor and founder of the TAMU Student Chapter of INMM (Fall 2004-present), this is the first student chapter in the over 40 year history of the organization.

American Nuclear Society
Member of the Technical Program Committee for the AccApp'03 (Nuclear Applications of Accelerator Technology) Conference to be held in San Diego, CA in the summer 2003
Chaired a technical session on neutronics calculations at the 2003 Annual ANS Meeting in San Diego
Member of the ANS Joint Benchmarking Committee (2003-present)
Chaired a technical session on advanced accelerator applications at the 2002 ANS Winter Meeting in Washington, DC
Chaired a technical session on the physics of nuclear reactors at the 2001 ANS Winter Meeting in Reno
Member of the ANS Standards Committee ANS 19 (2001-present)
Member of the Technical Program Committee and Student Programs Organizer for the 2002 ANS Radiation Protection and Shielding Division Topical Meeting held in Santa Fe, New Mexico (2001-2002)
Developed and organized a SOURCES-4A workshop for scientists, industry professionals, and students for the Year 2000 American Nuclear Society Radiation Protection and Shielding Division Topical Meeting held in Spokane, Washington on September 17, 2000
Participated in the ANS Reactor Physics Division Calvert Cliffs Benchmarking Committee (1999–present)
Organized a technical session entitled “Radiation Protection and Shielding Issues in Safeguards” at the 1999 ANS Winter Meeting in Long Beach, California
Member of the ANS Reactor Physics Division Program Committee (1999–present)
Member of the ANS Reactor Physics Division Review Committee (1998–present)
Co-author of the American Nuclear Society Standard ANS 19.3.4 (1999)
Member of the ANS 19.3.4 Standards Committee on energy deposition (1998–present)
Member (1997-2001) and Chair (2001-present) of the ANS 19.9 Standards Committee on delayed neutrons

GRANTS AND FUNDING
2006 Nuclear Security Science and Policy Institute, National Nuclear Security Administration
2006 Development and Application of Quantitative Proliferation Resistance Methodologies for Reprocessing Scenarios, Sandia National Laboratory
2005 Russian Academic Program in Nonproliferation and International Security, National nuclear Security Administration
2005 Development of an Undergraduate Neutron Counting Laboratory, Texas A&M University
2005 Pathways to Nuclear Terrorism, Los Alamos National Laboratory
2004 Watchdog, Los Alamos National Laboratory
2004 Scattered Neutron Tomography Based on a Neutron Transport Inverse Problem, U.S. Department of Energy
2004 Proliferation Resistance Assessments, Pacific Northwest National Laboratory
2004 Reactor-Accelerator Coupling Experiments, Idaho State University
2003 Development of a Method for Analyzing Signatures from a Radiological Dispersal Device, Los Alamos National Laboratory
2003 NuGET Experiment Validation, Sandia National Laboratory
2003 Stochastic Network Interdiction Models for Homeland Security, National Science Foundation
2002 Non-Proliferation Issues for Latin America: Argentinean and Brazilian Nuclear Power Plants and Reprocessing Facilities, Oak Ridge National Laboratory
2002 Support for LANL Transmutation Studies, Los Alamos National Laboratory
2001 Evaluating the Proliferation Resistance of ATW Options, Burns and Roe Enterprises, Inc.
2001 Nuclear Archaeology, Los Alamos National Laboratory
2001 Second Line of Defense, Los Alamos National Laboratory

PUBLICATIONS

Journal Articles

S.K. Aghara and W.S. Charlton, “Characterization and Quantification of an In-Core Neutron Irradiation Facility at a TRIGA II Research Reactor,” Nucl. Instrum. Meth. B, 248, 181-190 (2006).

M. Scott, W.S. Charlton, D.E. Burk, K. Epresi, D. Giannangeli, P.L. Knepper, A.S. Eberhardt, E. Leibrecht, and J.L. Ross, “Nuclear Forensics Inverse Technique for Attributing Material from a Spent Nuclear Fuel RDD Event,” submitted for publication to the Journal of Nuclear Science and Engineering (2005).

M. Scott, W.S. Charlton, D.E. Burk, K. Epresi, D. Giannangeli, P.L. Knepper, A.S. Eberhardt, E. Leibrecht, and J.L. Ross, “Attributing Unknown Spent Nuclear Fuel with NEMASYS,” submitted for publication to Science and Global Security (2005).

W.S. Charlton, A. Lumley-Woodyear, and K. Budlong-Sylvester, “The Feasibility of Verifying Plutonium Production from Nuclear Reactors Using Radionuclides in Structural Materials,” submitted for publication to Science and Global Security (2005).

D.E. Burk, W.S. Charlton, M. Scott, D. Giannangeli, and K. Epresi, “Forward Model Calculations for Determining Isotopic compositions of Materials Used in a Radiological Dispersal Device,” JNMM, 34(1), pp. 23-31 (2005).

S.R. Biegalski, T.C. Green, G.A. Sayre, W.S. Charlton, D.J. Dorsey, S. Landsberger, “Flux Weighted Efficiency Calibration of The University of Texas at Austin PGAA Facility,” J. Radioanalytical and Nuclear Chemistry, 265(2), pp. 303-308 (2005).

D.J. Dorsey, R. Hebner, W.S. Charlton, “Non-Destructive Evaluation of Carbon Fiber Composite Reinforcement Content,” Journal of Composite Materials, 38(17), pp. 1505-1519 (2004).

D.J. Dorsey, R. Hebner, and W.S. Charlton, “Application of Prompt Gamma Activation Analysis for the Determination of Water Content in Composite Materials,” J. Radioanalytical and Nuclear Chemistry,67, pp. 315-319 (2005).

D.J. Dorsey and W.S. Charlton, “Recent Developments and Applications for the University of Texas Thermal Neutron Imaging Facility,” J.Applied Radiation and Isotopes, 61, pp. 525-528 (2004).

W.S. Charlton, R.F. LeBouf, C. Gariazzo, D.G. Ford, C. Beard, S. Landsberger, and M. Whitaker, “Proliferation Resistance Assessment Methodology for Nuclear Fuel Cycles,” accepted for publication in the Journal of Nuclear Technology (2004).

L.D. Vickers and W.S. Charlton, “Radiological Assessment of Target Materials for Accelerator Transmutation of Waste Applications,” Nucl. Sci. and Eng., 145, pp. 354-375 (2003).

L. Vickers and W.S. Charlton, “Using NJOY99 and MCNP4B2 to Estimate the Radiation Damage Displacements per Atom per Second in Steel Within the Boiling Water Reactor Core Shroud and Vessel Wall from Reactor-Grade Mixed-Oxide/Uranium Oxide Fuel for the Nuclear Power Plant at Laguna Verde, Veracruz, Mexico,” Nucl. Sci. and Eng.145, pp. 376-389 (2003).

W.S. Charlton and J. Poths, “Capability of Ruthenium Isotopes in Distinguishing Fuel Type and Burnup,” JNMM, 31(2), pp. 5-10 (2003).

W.D. Stanbro, S. Hsue, T.L. Burr, M.L. Collins, C.A. Wells, W.S. Charlton and G.W. Eccleston, “Advanced Approaches to the International Oversight of Neptunium: Challenges and Opportunities,” JNMM, 30(2), pp. 60-65 (2002).

T. Burr, W.D. Stanbro, and W.S. Charlton, “An Evaluation of Safeguards Approaches for Neptunium,” J. Nucl. Sci. Technol., 38(3), p. 209-216 (2001).

W.S. Charlton and W.D. Stanbro, “Monitors for the Prediction of Alternate Nuclear Material Concentrations for PWR Spent Fuel,” Nucl. Tech., 136, pp. 24-36 (2001).

Y.V. Terekhine, T.A. Parish, and W.S. Charlton, “Shielding and Criticality Characterization of ALR8(SI) Plutonium Storage Containers,” J. Nucl. Sci. Technol., S1, pp. 347-351 (March 2000).

W.S. Charlton, R.T. Perry, G.P. Estes, and T.A. Parish, “Derivation and Implementation of the Three Region Problem in the SOURCES Code System,” J. Nucl. Sci. Technol., S1, pp. 570-574 (March 2000).

W.S. Charlton, W.D. Stanbro, and R.T. Perry, “Comparisons of HELIOS, ORIGEN2, and Monteburns Calculated 241Am and 243Am Concentrations to Measured Values for PWR, BWR, and VVER Spent Fuel,” J. Nucl. Sci. Technol., 37(7), pp. 615-623 (2000).

W.S. Charlton, R.T. Perry, and T.A. Parish, “Calculated Actinide and Fission Product Concentration Ratios for Gaseous Effluent Monitoring Using Monteburns 3.01,” Nucl. Tech., 131, pp. 210-227 (2000).

W.D. Stanbro, W.S. Charlton, P.H. Hemberger, J. Poths, T.L. Burr, and B.L. Fearey, “The Use of Stable Xenon Isotope Monitoring in Strengthened Safeguards at Large Reprocessing Plants,” JNMM, 28(2), p. 22 (2000).

W.S. Charlton, B.L. Fearey, C.W. Nahkleh, T.A. Parish, R.T. Perry, J. Poths, J.R. Quagliano, W.D. Stanbro, and W.B. Wilson, “Operator Declaration Verification Technique for Spent Fuel at Reprocessing Facilities,” Nucl. Inst. and Meth./B, 168, pp. 98 (2000).

W.S. Charlton, W.D. Stanbro, R.T. Perry, and B.L. Fearey, “Comparisons of Calculated and Measured 237Np, 241Am, and 243Am Concentrations as a Function of the 240Pu/ 239Pu Isotopic Ratio in Spent Fuel,” Nucl. Tech., 128, pp. 285-299 (1999).

N. Shinohara, Y. Hatsukawa, K. Hata, N. Kohno, M. Andoh, H. H. Saleh, W.S. Charlton, T.A. Parish, and S. Raman, “Measurements of Nuclear Data of Minor Actinides for Transmutation of High-Level Waste,” J. Rad. and Nucl. Chem., 239, pp. 631-638 (1999).

T.A. Parish, W.S. Charlton, N. Shinohara, M. Andoh, M.C. Brady, and S. Raman, “Status of Six Group Delayed Neutron Data and Relationships Between Delayed Neutron Parameters from the Macroscopic and Microscopic Approaches,” Nucl. Sci. and Eng . , 131, pp. 208-221 (1999).

W.S. Charlton, T.A. Parish, A.P. Belian, and C.A. Beard, “Measured and Calculated Radionuclide Production from Copper, Gold, and Lead Spallation Targets,” Nucl. Inst. and Meth. B, 142, pp. 9-16 (1998).

W.S. Charlton, R.T. Perry, and W.B. Wilson, “Benchmarking of the Los Alamos Neutron Production Rate Code SOURCES-3A,” Nucl. Inst. and Meth. B, 140, pp. 1-8 (1998).

Conference Proceedings

S. Vittorio and W.S. Charlton, “Scattered Neutron Tomography Based on a Neutron Transport Inverse Problem,” Trans. Am. Nucl. Soc., 93, 489-490 (2005).

W.S. Charlton, T. Woddi, S. O’Kelly, T. Green, and D. Beller, “Accelerator Driven Subcritical System Experiments at The University of Texas,” Trans. Am. Nucl. Soc., 93, 907-908 (2005).

S. O’Kelly, D. Beller, and W. Charlton, “Accelerator Driven Subcritical System Experiments at The University of Texas,” Trans. Am. Nucl. Soc., 93, 903 (2005).

M. Okano, T. Kuno, I. Takahashi, W.S. Charlton, C.A. Wells, P.H. Hemberger, “Development of Analysis Method for Plutonium Amount and Burn up by Measurement of Xenon Isotopic Ratio in Dissolver Off-gas at Reprocessing Facility,” presented at the 45 th Annual Meeting of the Institute for Nuclear Materials Management, Phoenix, Arizona, July 10-14, 2005.

D.E. Burk, W.S. Charlton, M. Scott, D. Giannangeli, and K. Epresi, “Forward Model Calculations for Determining Isotopic Compositions of Materials Used in a Radiological Dispersal Device,” presented at the 45 th Annual Meeting of the Institute for Nuclear Materials Management, Phoenix, Arizona, July 10-14, 2005.

A.A. Solodov and W.S. Charlton, “Study for the Formation of INMAC,” presented at the 45 th Annual Meeting of the Institute for Nuclear Materials Management, Phoenix, Arizona, July 10-14, 2005.

D.E. Burk, W.S. Charlton, M. Scott, D. Giannangeli, and K. Epresi, “Isotopic Compositions of Material Used in a Radiological Dispersal Device Determined by Forward Model Calculations,” Trans. Am. Nucl. Soc., 92, 674-675 (2005).

A.A. Solodov and W.S. Charlton, “Study of the Formation of INMAC,” presented at the 2005 Annual Meeting of the Southwest Chapter of the Institute for Nuclear Materials Management, Taos, New Mexico, May 20, 2005.

K.A. Miller and W.S. Charlton, “Inverse Transport Model for Identifying Source Position Near Portal Monitors,” presented at the 2005 Annual Meeting of the Southwest Chapter of the Institute for Nuclear Materials Management, Taos, New Mexico, May 20, 2005.

D.E. Burk, W.S. Charlton, M. Scott, D. Giannangeli, K. Epresi, and P.L. Knepper, “Uncertainty Estimates in Spent Fuel Isotopics Using Post-Irradiation Examination of Spent Fuel Dissolution,” presented at the 2005 ESARDA meeting, London, England, May 9-12, 2005.

W.S. Charlton, M. Scott, D.E. Burk, K. Epresi, D. Giannangeli, P.L. Knepper, A.S. Eberhardt, E. Leibrecht, and J.L. Ross, “Nuclear Forensics Technique for Attributing Spent Nuclear Fuel,” presented at the 2005 ESARDA meeting, London, England, May 9-12, 2005.

S. O’Kelly, T. Green, and W. Charlton, “Reactor Accelerator Coupled Experiment (RACE) at The University of Texas at Austin,” Trans. Am. Nucl. Soc., 91, pp. 445-446 (2004).

W.S. Charlton, D.G. Ford, R.F. LeBouf, and C. Gariazzo, “Proliferation Resistance Assessments Methodology for Nuclear Fuel Cycles,” presented at the 44 th Annual Meeting of the Institute for Nuclear Materials Management, Orlando, Florida, July 18-22, 2004.

W.S. Charlton, M. Scott, D.E. Burk, K. Epresi, D. Giannangeli, P.L. Knepper, A.S. Eberhardt, E. Leibrecht, and J.L. Ross, “Nuclear Forensics Technique for Attributing Material Used in a Radiological Dispersal Device Event,” presented at the 44 th Annual Meeting of the Institute for Nuclear Materials Management, Orlando, Florida, July 18-22, 2004.

W.S. Charlton and V.K. Taraknath Woddi, “Reactor-Accelerator Coupled Experiments (RACE): A Feasibility Study at TAMU,” Proceedings of the PHYSOR 2004 Conference, Chicago, Illinois, April 25-29, 2004.

W.S. Charlton, G. Sayre, S. Biegalski, T. Green, and S. Landsberger, “Comparison of Measured and Calculated Prompt Gamma Ray Yields and Spectra for Verification of MCNP5,” presented at the 14 th Pacific Basin Nuclear Conference, Honolulu, Hawaii, March 21-25, 2004.

W.B. Wilson, R.T. Perry, W.S. Charlton, T.A. Parish, and E.F. Shores, “SOURCES: A Code for Calculating (Alpha,N), Spontaneous Fission, and Delayed Neutron Sources and Spectra,” presented at the 10 th International Conference on Radiation Shielding, Madeira Island, Portugal, May 9-14, 2004.

W.S. Charlton, R.F. LeBouf, and S. Aghara, “Proliferation Resistance Assessment Methodology for Analyzing ATW Fuel Cycles,” Proceedings of the Sixth International Meeting on Nuclear Applications of Accelerator Technology (AccApp’03), pp. 930-939, San Diego, California, June 1-5, 2003.

D.J. Dorsey and W.S. Charlton, “Measured Energy Spectra of the 10B(n, a ) 7Li* Recoil De-Excitation in Media of Different Density,” Trans. Am. Nucl. Soc., 89, pp. 725-726 (2003).

W.S. Charlton and D.J. Dorsey, “Measurement of the Neutron Energy Spectrum in the PGAA Facility at the University of Texas,” Trans. Am. Nucl. Soc., 89, pp. 729-730 (2003).

S.R. Biegalski, T.C. Green, G.A. Sayre, W.S. Charlton, and S. Landsberger, “Flux Weighted Efficiency Calculations at The University of Texas at Austin PGAA Facility,” Trans. Am. Nucl. Soc., 89, pp. 731-732 (2003).

S.K. Aghara, R.J. Fink, W.S. Charlton, B. Bhuva, M.R. Samadi, J.A. Ochoa, and J.R. Porter, “Degradation of Commercially Available DAC ICs in Mixed Degradation of Commercially Available DAC ICs in Mixed-Radiation Environment,” presented at the 2003 IEEE Nuclear Space Radiation Effects Conference (NSREC), Monterey, CA, July 21-25, 2003.

W.S. Charlton, D.G. Ford, C. Gariazzo, and M. Whitaker, “Development of a Proliferation Resistance Analysis Methodology for Assessing Safeguards Effects in Fuel Cycles,” presented at the 43 rd Annual Meeting of the Institute for Nuclear Materials Management, Phoenix, Arizona, July 14-18, 2003.

S.K. Aghara, W.S. Charlton, R. Fink, J.A. Ochoa, and J. Porter, “Fast Neutron Damage to Digital-to-Analog Converters in a Mixed Radiation Environment,” Trans. Am. Nucl. Soc., 88, pp. 63-65 (2003).

D.J. Dorsey, W.S. Charlton, and R. Hebner, “Experimental Measurements of Fiber Volume in Carbon Composites Using PGAA,” Trans. Am. Nucl. Soc., 88, pp. 664-665 (2003).

D.J. Dorsey and W.S. Charlton, “Experiments to Measure the Variations in the Neutron Flux Delivered by the Texas Cold Neutron Source,” Trans. Am. Nucl. Soc., 88, pp. 666-668 (2003).

M. Gregson and W.S. Charlton, “Analysis of Radiation Detection Systems for Detecting the Illicit Trafficking of Nuclear Materials,” presented at the 6 th International Conference on the Methods and Applications of Radioanalytical Chemistry (MARC VI), Kailua-Kona, Hawaii, April 7-11, 2003.

W.S. Charlton, A. de Lumley-Woodyear, and K. Sylvester, “Estimating Discharged Plutonium Using Measurements of Structural Material Activation Products,” Trans. Am. Nucl. Soc., 86, pp. 337-339 (2002).

L.D. Vickers and W.S. Charlton, “Radiological Assessment of Target Materials for ATW Applications,” Trans. Am. Nucl. Soc., 86, pp. 423-425 (2002).

D.J. Dorsey, W.S. Charlton, and R. Hebner, “Experimental Measurements of Water Content in Carbon Composites Using PGAA,” Trans. Am. Nucl. Soc., 86, pp. 389-391 (2002).

S.K. Aghara, W.S. Charlton, and D.S. O’Kelly, “Characterization of an In-Core Location at the University of Texas TRIGA II for Electronic Hardness Assurance Testing,” Trans. Am. Nucl. Soc., 86, pp. 359-360 (2002).

D.J. Dorsey, W.S. Charlton, and R. Hebner, “Cold Neutron Prompt Gamma-Ray Activation Analysis for the Non-Destructive Evaluation of Composite Material Elemental Constituents,” Proceedings of the 4 th International Conference on Mechanics and Materials in Design, p. 34, Nagoya, Japan, June 5-8, 2002.

D.J. Dorsey and W.S. Charlton, “ Monte Carlo Evaluation of a New Reflector for the UT TRIGA Reactor,” Trans. Am. Nucl. Soc., 85, p. 418 (2001).

K. Pandey, D.J. Dorsey, W.S. Charlton, and R. Hebner, “Reproducibility Experiments and Optimization of the Neutron and Gamma-Ray Shielding for the UT PGAA System,” Trans. Am. Nucl. Soc., 85, p. 437 (2001).

C.A. Wells, W.S. Charlton, and W.D. Stanbro, “Using Reactor Models to Predict Physical Material Content of Spent Fuels: Applications to Nuclear Materials Oversight,” presented at the 42 nd Annual Meeting of the Institute for Nuclear Materials Management, Indian Wells, California, July 15-19, 2001.

Sheldon Landsberger, William Charlton, Carl Beard and Marsha Creatchman, “Graduate Distance Learning in Nuclear and Radiation Engineering at the University of Texas at Austin,” presented at Annual Meeting of the American Society for Engineering Education, Albuquerque, New Mexico, June 2001.

D.J. Dorsey and W.S. Charlton, “Recent Developments and Applications for the University of Texas Thermal Neutron Imaging Facility,” presented at the 4 th International Topical Meeting on Neutron Radiography, State College, Pennsylvania, June 3-6, 2001.

W.S. Charlton and D.J. Dorsey, “Preliminary Experiments to Determine Moisture in Carbon Composites Using PGAA,” Trans. Am. Nucl. Soc., 84, pp. 131-132 (2000).

D.J. Dorsey and W.S. Charlton, “Redesign of the UT Thermal Neutron Imaging Facility Shielding,” Trans. Am. Nucl. Soc., 84, pp. 132-133 (2000).

C.A. Wells, W.D. Stanbro, and W.S. Charlton, “Monitors for Prediction of Neptunium and Americium Concentrations in Spent Fuel,” presented at the 23rd Annual Meeting Symposium on Safeguards and Nuclear Materials Management, Bruges, Belgium, May 8-10, 2001.

F. Pan, W.S. Charlton, and D. Morton, “Stochastic Interdiction Applications to Smuggling Networks,” presented at the 2001 Annual Meeting of the Southwest Chapter of the Institute for Nuclear Materials Management, Taos, New Mexico, May 4, 2001.

T.H. Brown, R.T. Perry, W.B. Wilson, and W.S. Charlton, “Thick-Target ( a ,n) Neutron Yields and Spectra Calculated with ORIGEN-S and SOURCES,” presented at the Year 2000 American Nuclear Society Radiation Protection and Shielding Division Topical Meeting, Spokane, Washington, September 17-21, 2000.

W.S. Charlton, T. Burr, W.D. Stanbro, K. Budlong-Sylvester, and J. Gattiker, “Simulation Tool for Predicting Classical Epidemiology Data for Infectious Diseases Using a Probabilistic Model,” presented at the 2000 International Conference on Mathematics and Engineering Techniques in Medicine and Biological Sciences, Las Vegas, Nevada, June 26-29, 2000.

W.S. Charlton, T. Burr, and W.D. Stanbro, “Comparison of Signature Pattern Analysis Methods in Molecular Epidemiology,” presented at the 2000 International Conference on Mathematics and Engineering Techniques in Medicine and Biological Sciences, Las Vegas, Nevada, June 26-29, 2000.

W.S. Charlton, W.D. Stanbro, and R.T. Perry, “Comparisons of Calculated and Measured 241Am and 243Am Concentrations in PWR and VVER Spent Fuel,” presented at the PHYSOR 2000 International Topical Meeting, Pittsburgh, Pennsylvania, May 7-11, 2000.

W.S. Charlton, R.T. Perry, T.A. Parish, and P.H. Hemberger, “Burnup and Age Dating of Spent Nuclear Fuel Using Noble Gas Isotopic Analysis,” Trans. Am. Nucl. Soc., 81, p. 312 (1999).

T.A. Parish, Y.V. Terekhine, and W.S. Charlton, “Shielding Analysis for ALR8 and ALR8(SI) Pit Storage Containers,” Trans. Am. Nucl. Soc., 81, p. 241 (1999).

T.A. Parish, Y.V. Terekhine, and W.S. Charlton, “Shielding and Criticality Characterization of ALR8(SI) Plutonium Storage Containers,” Proceedings of the 1999 Researchers’ Conference, Amarillo, Texas, July 19-21, p. 27, Amarillo National Resource Center for Plutonium (1999).

R.T. Perry, W.S. Charlton, P.L. Knepper, K.E. Apt, J. Ramirez Sanchez, M. Lucatero, and J. Palacios Hernandez, “US-Mexican Collaboration in Computational Research for the Peaceful Use of Nuclear Energy,” presented at the International Joint Meeting of the Mexican Nuclear Society on The Role of Nuclear Power to Mitigate Climate Change, Acapulco, Mexico, July 18-21, 1999.

W.S. Charlton, R.T. Perry, and T.A. Parish, “Monteburns and HELIOS Calculated Spent Fuel Isotopics Compared to Measured Values,” Trans. Am. Nucl. Soc., 80, p. 274 (1999).

W.S. Charlton, W.D. Stanbro, B.L. Fearey, P.H. Hemberger, R.T. Perry, and J. Poths, “The Use of Stable Noble Gases to Confirm Compliance with the Fissile Material Cutoff Treaty,” Proceedings of the Sixth International Conference on Facility Operations – Safeguards Interface, Jackson Hole, WY, September 20-24, p. 212-219, American Nuclear Society (1999).

B.L. Fearey, W.S. Charlton, R.T. Perry, J. Poths, W.D. Stanbro, and W.B. Wilson, “The Use of Stable Noble Gases as a Predictor of Reactor Fuel Type and Exposure,” presented at the Global ’99 International Conference on Future Nuclear Systems in Jackson Hole, Wyoming, August 30-September 2, 1999.

B.L. Fearey, W.S. Charlton, P.H. Hemberger, R.T. Perry, J. Poths, W.D. Stanbro, and W.B. Wilson, “The Use of Stable Noble Gases for Safeguard Applications,” presented at the 40 th Annual Meeting of the Institute of Nuclear Materials Management, Phoenix, Arizona, July 25-29, 1999.

W.S. Charlton, C.W. Nahkleh, R.T. Perry, J. Poths, J.R. Quagliano, W.D. Stanbro, and B.L. Fearey, “Safeguards for Reprocessing Facilities through On-Stack Environmental Monitoring,” Proceedings of the 21st Annual Meeting Symposium on Safeguards and Nuclear Material Management, Sevilla, Spain, May 4-6, p. 869, Joint Research Center of the European Commission (1999).

L. Angers, W.S. Charlton, and T.A. Parish, “Importance of Decay Chains in Calculating Delayed Neutron Emission Rates from Fission Product Yield Data,” Trans. Am. Nucl. Soc., 79, p. 310 (1998).

W.S. Charlton, C. Comfort, T.A. Parish, and S. Raman, “Measured Delayed Neutron Spectra from the Fission of U-235 and Np-237,” Trans. Am. Nucl. Soc., 79, p. 309 (1998).

W.S. Charlton and T.A. Parish, “Alpha-Particle Source Rate and Spectra at the Surface of a Spherical Source Particle,” Trans. Am. Nucl. Soc., 79, p. 274 (1998).

W.S. Charlton, R.T. Perry, B.L. Fearey, and T.A. Parish, “Comparisons of HELIOS Calculated Isotope Concentrations to Measured Values for Several Reactor Systems,” presented at the CMS/FMS Users Group Meeting, Madrid, Spain, October 21-23, 1998.

W.S. Charlton, T.A. Parish, and S. Raman, “Preliminary Pulsing Experiments to Measure Delayed Neutron Emission Parameters,” International Conference on the Physics of Nuclear Science and Technology, Long Island, New York, October 5-8, p. 190, American Nuclear Society (1998).

R.T. Perry, W.B. Wilson, and W.S. Charlton, “SOURCES-3A: A Code for Calculating ( a ,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra,” Proceedings of the 1998 American Nuclear Society Topical Meeting on Radiation Protection and Shielding, Nashville, Tennessee, April 19-23, Volume 2, pp. 348-355 (1998).

R.T. Perry, R.D. Mosteller, P. Chodak III, W.S. Charlton, and B.T. Adams, “HELIOS: Applications at Los Alamos National Laboratory,” presented at the 15th Fuel Management System User Group Meeting, Budapest, Hungary, October 30-31, 1997.

B.T. Rearden, T.A. Parish, and W.S. Charlton, “Generation of Two-Group Cross Sections for WG-MOX Fuel Using MCNP,” Trans. Am. Nucl. Soc., 77, p. 323 (1997).

W. Charlton, T. Parish, S. Raman, N. Shinohara, and M. Andoh, “Delayed Neutron Emission Measurements for Fast Fission of U-235, Np-237, and Am-243,” Proceedings of the International Conference on Nuclear Data for Science and Technology, Trieste, Italy, p. 491, Italian Physical Society (1997).

W.S. Charlton, T.A. Parish, S. Raman, N. Shinohara, and M. Andoh, “Delayed Neutron Emission Measurements from Fast Fission of U-235 and Np-237,” Proceedings of the International Conference on the Physics of Reactors, Mito, Japan, p. F-11, Japan Atomic Energy Research Institute (1996).

W. Charlton and T. Parish, “Radioisotopes Produced in a Lead Foil Bombarded by 125 MeV Deuterons,” Trans. Am. Nucl. Soc., 74, p. 335 (1996).

Book Chapters

F. Pan, W.S. Charlton, and D.P. Morton, “A Stochastic Program for Interdicting Smuggled Nuclear Material,” to appear in Network Interdiction and Stochastic Integer Programming,
J. De Loera and D.L. Woodruff (eds.), Kluwer Academic Publishers (2002).

T.A. Parish and W.S. Charlton, “Delayed Neutron Data for Actinides Obtained from Global Level Measurements,” Safety Issues Associated with Plutonium Involvement in the Nuclear Fuel Cycle, T. A. Parish, ed., p. 213-224, Kluwer Academic Publishers, Dordecht, Netherlands (1999).

Government Reports

W.B. Wilson, R.T. Perry, W.S. Charlton, T.A. Parish, G.P. Estes, T.H. Brown, E.D. Arthur, M. Bozoian, T.R. England, D.G. Madland, and J.E. Stewart, “SOURCES 4A: A Code for Calculating (?,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra,” LA-13639-MS, Los Alamos National Laboratory (1999).

W.S. Charlton, “Noble Gas Measurement and Analysis Technique for Monitoring Reprocessing Facilities,” LA-13636-T, Los Alamos National Laboratory (1999).
T.H. Brown, W.B. Wilson, R.T. Perry, and W.S. Charlton, “Comparison of (alpha,n) Thick-Target Yields and Spectra from ORIGEN-S and SOURCES,” LA-UR-98-3094, Los Alamos National Laboratory (1998).

R.T. Perry, W.B. Wilson, T.A. Parish, and W.S. Charlton, “SOURCES-3A: A Code for Calculating Alpha,N; Spontaneous Fission; and Beta-N Delayed Neutron Sources and Spectra,” LA-UR-96-3869, Los Alamos National Laboratory (1997).

W.S. Charlton, “GEM 1A: A Generalized Grid Generation Code,” LA-UR-97-3394, Los Alamos National Laboratory (1997).

W.B. Wilson, R.T. Perry, W.S. Charlton, E.D. Arthur, M. Bozoian, T.H. Brown, T.R. England, D.G. Madland, T.A. Parish, and J.E. Stewart, “SOURCES-3A: A Code for Calculating (?,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra,” LA-UR-97-4365, Los Alamos National Laboratory (1997).