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5 11

3. N. M. Abdurrahman and A. P. Simpson, Die-Away Assay: A New Radwaste

Measurement System Offers a Viable Alternative to Dose To Curie Method, Nuclear

Engineering International, Wilmington Media, UK, July 2007

4. N. M. Abdurrahman and A. P. Simpson, High Sensitivity Neutron Assay of Grouted

Spent Nuclear Fuel Sludge at Hanford, American Nuclear Society

Transactions/European Nuclear Society, 2007 ANS/ENS International Meeting,

Washington, DC, November 11-17, 2007.

5. N. M. Abdurrahman, A. Simpson, and S. Barber, WIPP Certification of a New

SuperHENC Box Counter at Hanford, Trans. Am. Nucl. Soc., 93, 819-820 (2005).

6. L. Eric Smith and Naeem M. Abdurrahman, "Neutron Spectrometry for the Assay of

High Fissile Content Spent Fuel," Nuclear Technology, 142, to Appear in Dec. 2002.

7. Y. D. Lee, M. M. Abdurrahman, R. C. Block, D. R. Harris, and R. E. Slovacek, Design

of a Spent Fuel Assay Device Using Lead Spectrometer, Nuc. Sci. Eng. 131, 45-61

(1999).

8. A. Hawari, B. W. Wehring, and N. M. Abdurrahman, Feasibility of Using a Graphite

Slowing-Down-Time Spectrometer in the Nondestructive Assay of Nuclear Materials,

Nuclear Instruments and Methods, 422, 846-851 (1999).

9. H. Akkurt and N. M. Abdurrahman, Benchmark Calculations of the Esada Single Region

Mixed-Oxide Critical Experiments, Nuclear Technology, 127, 301-314 (1999).

10. M. M. Abdurrahman, G. Radulescu, and I. Carron, Benchmark Calculations of the

Saxton Plutonium Program Critical Experiments, Nuclear Technology, 127, 315-331

(1999).

11. M. S. Abdelrahman and N. M. Abdurrahman, Imaging Automation and Volume

Tomographic Visualization at Texas Neutron Imaging Facility, Trans. Am. Nucl. Soc.,

81, 120-121 (1999).

12. M. A. Elsawi, N. M. Abdurrahman, and M. Yavuz, Simplified Discrete Ordinates

Method in Spherical Geometry, Trans. Am. Nucl. Soc., 81, 136-138 (1999).

13. Y. G. Jo, N. M. Abdurrahman and M. S. Abdelrahman, New Thermal Neutron Imaging

Facility at The University of Texas Reactor, Trans. Am. Nucl. Soc., 80, 84-85 (1999).

14. N. M. Abdurrahman, Y. G. Jo and M. S. Abdelrahman, Demonstration of Neutron

Radiography and Computed Tomography at The University of Texas Thermal Neutron

Imaging Facility, Trans. Am. Nucl. Soc., 80, 85-87 (1999).

15. M. S. Abdelrahman and N. M. Abdurrahman, UTXS Cross Section Library for Analysis

of Mixed Oxide Water Reactor Cores, Trans. Am. Nucl. Soc., 79, 177-179 (1998).

16. M. Yavuz and N. M. Abdurrahman, Inverse Simplified SN Method for Multigroup

Eigenvalues of Slab Geometry Transport Problems, Trans. Am. Nucl. Soc., 76, 216-217

(1997).

6 11

17. M. A. Elsawi, N. M. Abdurrahman, B. W. Wehring, and A. I. Hawari, The Use of

Graphite for Slowing-Down-Time Spectrometry, Trans. Am. Nucl. Soc., 76, 139-140

(1997).

18. N. M. Abdurrahman, M. A. Elsawi, and D. R. Harris, Resolution Function in Slowing

Down Time Spectrometers, Trans. Am. Nucl. Soc., 77, 188-190 (1997).

19. N. M. Abdurrahman, Y. G. Jo, W. J. Spiesman, and T. L. Bauer, Verification of MCNP

Model for the University of Texas TRIGA Reactor, Trans. Am. Nucl. Soc., 77, 132-134

(1997).

20. N. M. Abdurrahman and M. Yavuz, MCNP Analysis of Split-Table Critical Experiments

Containing Mixed Oxide Fuels, Trans. Am. Nucl. Soc., 77, 213-215 (1997).

21. Y. G. Jo, N. M. Abdurrahman, B. W. Wehring, Design of a Neutron Radiography

Collimator System in a Through Beam Port at Triga Reactor, Trans. Am. Nucl. Soc., 75,

113-114 (1996).

22. N. M. Abdurrahman and B. W. Wehring, "Neutron Imaging System for Neutron

Radiography, Tomography, and Beam Diagnostics," Trans. Am. Nucl. Soc., 73, 154-155

(1995).

23. K. P. Cheng, K. Unlu, A J. Teachout, N. M. Abdurrahman, and B. W. Wehring,

"Gadolinium Neutron Capture Therapy Dosimetry Measurements," Trans. Am. Nucl.

Soc., 73, 30-31 (1995).

24. N. M. Abdurrahman, R. C. Block, D. R. Harris, F. Rodriguez-Vera and R. E. Slovacek,

"Spent Fuel Assay Performance and Monte Carlo Analysis of Rensselaer Slowing-Down-

Time Spectrometer," Nucl. Sci. Eng., 115, 279-296 (1993).

25. N. M. Abdurrahman, R. C. Block, D. R. Harris and R. E. Slovacek, "Sensitivity Analysis

of the Resolution Function of Rensselaer SDT Spectrometer," Trans. Am. Nucl. Soc., 66,

477-478 (1992).

26. D. R. Harris, F. Rodriguez-Vera, N. M. Abdurrahman, Y. D. Lee, R. E. Slovacek and R.

C. Block, "Measurement of Uranium and Plutonium Content in a Fuel Assembly Using

the RPI Spent Fuel Assay Device," Trans. Am. Nucl. Soc., 61, 73-74 (1990).

Refereed Conference Proceedings

1. Mark A. Gilbertson, Kurt D. Gerdes, John L. Wengle, Naeem M. Abdurrahman, A

National Academies Study on Waste Form Technology and Performance, Waste

Management Conference, Tucson, AZ (2010), Accepted.

2. P. Simpson and N. M. Abdurrahman, High Sensitivity Assay of Cement Encapsulated

Spent Nuclear Fuel Sludge Using the Imaging Passive Active Neutron (IPAN) System,

Waste Management Conference, Tucson, AZ (2007)

3. Simpson, S. Barber, N. M. Abdurrahman, Innovations in the Assay of Un-segregated

Multi-isotopic Grade TRU Waste Boxes with SuperHENC and FRAM Technology,

Annual Waste Management Conference, Tucson, Arizona (2006).

7 11

4. M. A. Elsawi, N. M. Abdurrahman, Y. Y. Azmy, "Asymptotic Analysis of the Spatial

Weights of the Arbitrarily High Order Transport Method of the Characteristic Type,

Nuclear Mathematical and Computational Sciences, A Century in Review, A Century

Anew, American Nuclear Society, Gatlinburg, Tennessee (2003).

5. Y. G. Jo M. A. Abdelrahman and N. M. Abdurrahman, Nondestructive Evaluation of

Aluminum Honeycomb Structures Using Thermal Neutron Radiography, Proc. 2000

NSF Design and Manufacturing Research Conference (2000)

6. Y. G. Jo, M. S. Abdelrahman, and N. M. Abdurrahman, Selective Nondestructive

Evaluation Applications of Thermal Neutron Imaging, Proc. 8th International

Conference on Nuclear Engineering, American Society of Mechanical Engineers, New

York, NY (2000)

7. N. M. Abdurrahman and L. E. Smith, Modeling of a Lead Spectrometer for the Assay of

High Fissile Content Mixed Oxide Fuel, Proc. 8th International Conference on Nuclear

Engineering, American Society of Mechanical Engineers, New York, NY (2000)

8. W. Mosby, L. E. Smith, and N. M. Abdurrahman, Development of a Shielded

Measurement System for Dry Irradiated Nuclear Fuel, Proc. 41st Annual Meeting,

Institute of Nuclear Materials Management, New Orleans, LA (2000)

9. Y. G. Jo and N. M. Abdurrahman, "The Effect of Moderating Piece Inside a Neutron

Collimator on Neutron Dose Around Neutron Imaging Facility," Proc. 1998 Radiation

and Shielding Division Topical Conference: Technologies for the New Century,

American Nuclear Society, Vol. I, pp. 11-117 (1998).

10. G. Radulescu, M. Yavuz, H. Akkurt, N. M. Abdurrahman, B. T. Rearden, G. F. Cuevas-

Vivas, J. A. Cowan, and T. A. Parish, Neutronics Benchmarks for the Utilization of

Mixed Oxide Fuel, in Nuclear Materials Safety Management, K.L. Peddicord, L.N.

Lazareve, and L.J. Jardine, Eds, Disarmament Technologies - Vol. 20, Kluwer Academic

Publishing, pp. 271-279 (1998)

11. N. M. Abdurrahman, B. W. Wehring, T. L. Bauer, Y. G. Jo, Development of Neutron

Imaging System for Real Time Neutron Radiography and Neutron Computed

Tomography at The University of Texas Triga Reactor, Proc. 5th World Conf. Neutron

Radiography, Deutsche Gesellschaft fr Zerstrungsfreie Prfung, pp. 222-228 (1997)

12. Y. D. Lee, N. M. Abdurrahman, R. C. Block, and R. E. Slovacek, "Neutron Emission

Tomography for Nuclear Fissile Materials Safeguards," Proc. 5th Int. Conf. Facility

Operations-Safeguards Interface, pp. 200-204 (1996).

13. Boumakh and N. M. Abdurrahman, "Geodesic Formulation of Magnetic Field Lines in

Toroidal Fusion Systems," Proc. IEEE Int. Conf. Plasma Science, (1995).

14. N. M. Abdurrahman, R. C. Block, D. R. Harris, F. Rodriguez-Vera and R. E. Slovacek,

"Development of the Lead Slowing Down Time Spectrometer at RPI for Nuclear Fuel

Assay," Proc. 4th Int. Conf. Facility Operations-Safeguards Interface, pp. 374-380

8 11

(1992).

Technical Reports

1. M. D. DeHart, J. C. Gehin, H. T. Hunter, J. J. Lichtenwalter, B. D. Murphy, R. T. Primm,

III, I. Remec, N. M. Abdurrahman, I. J. Carron, T. A. Parish, G. Radulescu, E. J. Reott,

and M. Yavuz, Neutronics Benchmarks for the Utilization of Mixed Oxide Fuel - Initial

Progress Report for Fiscal Year 1997, Oak Ridge National Laboratory, Feb. 1997.

2. M. D. DeHart, J. C. Gehin, I. Remec, R. T. Primm, III, N. M. Abdurrahman, I. J. Carron,

T. A. Parish, and G. Radulescu, Neutronics Benchmarks for the Utilization of Mixed

Oxide Fuel - Updated Progress Report for Fiscal Year 1997, Vol. II - Computational

Benchmarks, Oak Ridge National Laboratory, May, 1997.

3. P. B. Fox, J. J. Lichtenwalter, B. D. Murphy, R. T. Primm, III, N. M. Abdurrahman, G.

Radulescu, and M. Yavuz, Neutronics Benchmarks for the Utilization of Mixed Oxide

Fuel - Updated Progress Report for Fiscal Year 1997, Vol. III - Experimental

Benchmarks, Oak Ridge National Laboratory, May, 1997.

4. M. D. DeHart, H. T. Hunter, R. T. Primm, III, N. M. Abdurrahman, I. J. Carron, T. A.

Parish, G. Radulescu, E. J. Reott, and M. Yavuz, Neutronics Benchmarks for the

Utilization of Mixed Oxide Fuel - Updated Progress Report for Fiscal Year 1997, Vol. IV

- Evaluations of Critical Experiments, Oak Ridge National Laboratory, May, 1997.

5. M. S. Abdelrahman and N. M. Abdurrahman, Cross Sections Libraries for Studies of

Plutonium Disposition in Light Water Reactor, Amarillo National Resource Center for

Plutonium, ANRCP-1999-28, October 1999.

6. N. M. Abdurrahman, Interval Estimation for Statistical Control Limits, HNF-11976,

Fluor Hanford, May 2002

7. N. M. Abdurrahman and T. J. Southworth, Performance Control Limits for Gamma Assay

Systems, HNF-11977, Fluor Hanford, August 1, 2002

8. N. M. Abdurrahman and P. G. Loscoe, K Basins 100K-03-0308 Standard Waste Box

Assay on The SuperHENC at WRAP, Fluor Hanford, April 29, 2005

9. N. M. Abdurrahman, Calibration and Validation Report for the WRAP Super High

Efficiency Coincidence (SuperHENC) Mobile Assay System, HNF-26085, Fluor

Hanford, May 2005

10. N. M. Abdurrahman, WRAP Imaging Passive Active Neutron (IPAN) Systems Software

V&V Document, HNF-16731, Fluor Hanford, May 2005

11. N. M. Abdurrahman, WRAP Drum Imaging Passive Active Neutron (IPAN) Systems

TMU Report, HNF-16730, Fluor Hanford, May 2005

12. N. M. Abdurrahman, WRAP Imaging Passive Active Neutron (IPAN) System Calibration

Test Report, HNF-16729, Fluor Hanford, May 2005

13. K. I. Husted and N. M. Abdurrahman, Calibration Report for the WRAP Facility GEA

System Unit A, HNF-5148, Fluor Hanford, May 2005

9 11

14. N. M. Abdurrahman, WRAP NDA Certified Radioactive Sources, HNF-9787, Rev. 0-B,

Fluor Hanford, June 2005

15. N. M. Abdurrahman and K. I. Husted, Total Measurement Uncertainty for Nondestructive

Assay of Transuranic Waste at the Waste Receiving and Processing Facility, HNF-4050,

Rev. 10, Fluor Hanford, July 2005

16. K. I. Husted and N. M. Abdurrahman, Calibration Report for the WRAP Facility GEA

System Unit B, HNF-5149, Fluor Hanford, March 2006

17. N. M. Abdurrahman, SuperHENC Calibration Report for 110 Gallon Puck Drum Assay

(Calibration Curve Method), HNF-37599, Fluor Hanford, May 2008

Selected Oral Presentations

1. Nondestructive Assay at the Waste Receiving and Processing Facility, Department of

Energy Facility Representatives Meeting, Richland, WA, January 24, 2008.

2. Decommissioning, Decontamination, and Reutilization Technology (Panel Discussion),

American Nuclear Society Transactions/European Nuclear Society, 2007 ANS/ENS

International Meeting, Washington, DC, November 11-17, 2007.

3. High Sensitivity Neutron Assay of Grouted Spent Nuclear Fuel Sludge at Hanford,

American Nuclear Society Transactions/European Nuclear Society, 2007 ANS/ENS

International Meeting, Washington, DC, November 11-17, 2007.

4. High Sensitivity Assay of Cement Encapsulated Spent Nuclear Fuel Sludge Using The

Imaging Passive Active Neutron (IPAN) System, Waste Management 2007 Conference

(WM'07), Tucson, AZ, February 25 - March 1, 2007.

5. Innovations in the Assay of Un-segregated Multi-isotopic Grade TRU Waste Boxes with

SuperHENC and FRAM Technology, 32nd Annual Waste Management Conference,

Tucson, Arizona, February 26 March 2, 2006

6. WIPP Certification of a New SuperHENC Box Counter at Hanford, American Nuclear

Society Winter Meeting, Washington, D.C., November 13, 2005.

7. Seminar on Neutron Slowing Down Time Spectrometry for Spent Nuclear Fuel

Characterization, IU Cyclotron Facility, Indiana University, Bloomington, Indiana,

August 29, 2001.

8. Seminar on Neutron Slowing Down Time Spectrometry for Spent Nuclear Fuel

Characterization, IU Cyclotron Facility, Indiana University, Bloomington, Indiana,

August 29, 2001.

9. Seminar on Utilization of Accelerators for Nondestructive Assay of Nuclear Materials,

Advanced Photon Source (APS), Argonne National Laboratory, August, 2001

10. Seminar on Computational Methods in Nuclear Science and Engineering, Lawrence

Livermore National Laboratory, June 2001

11. Feasibility of National Spent Nuclear Fuel Assay using Lead Slowing Down Time

Spectrometry, Argonne National Laboratory, Idaho Falls, ID, July 22, 1999.

11 11

12. Saxton Critical Experiments: Sensitivity Calculations for PuO2 Particle Size, Fifth United

States/Russia Technical Specialists Meeting on Water Reactors for Fissile Materials

Disposition, Oak Ridge, TN, November 11-13, 1998.

13. Criticality and Power Distribution Calculations of Single and Multiregion Esada

Experiments Using MCNP, Fifth United States/Russia Technical Specialists Meeting on

Water Reactors for Fissile Materials Disposition, Oak Ridge, TN, November 11-13,

1998.

14. Saxton Critical Experiments: Criticality and Power Distribution Calculations, Fourth

United States/Russia Technical Specialists Meeting on Water Reactors for Fissile

Materials Disposition, St. Petersburg, Russia, June. 17-19, 1998.

15. Calculations of Single and Multiregion Esada Experiments with MCNP, Fourth United

States/Russia Technical Specialist Meeting on Water Reactors for Fissile Materials

Disposition, St. Petersburg, Russia, June. 17-19, 1998.

16. New Thermal Neutron Imaging Facility at The University of Texas Triga Reactor," 9th

Symposium on Radiation Measurements & Applications, Ann Arbor, MI, 1998.

17. MCNP Calculations for CS3, CS4 and PNL Criticality Safety Benchmarks, Third United

States/Russia Technical Specialists Meeting on Water Reactors for Fissile Materials

Disposition, Oak Ridge, TN, August 24-27, 1997.

18. Slowing Down Time Spectrometry Methods for Nondestructive Assay, NATO Advanced

Research Workshop, Amarillo, TX, March 17-21, 1997.

19. Neutronics Benchmarks for the Utilization of Mixed Oxide Fuel, NATO Advanced

Research Workshop, Amarillo, TX, March 17-21, 1997.

20. Amarillo National Resource Center for Plutonium and Weapons Plutonium Disposition,

OECD/NEA Criticality Safety Group Meeting, Paris, June 27, 1996.

21. The Use of Lead Slowing Down Time Spectrometry for Nondestructive Assay of Fissile

Materials, Los Alamos National Laboratory, Los Alamos, NM, Sep. 6, 1996.

22. Amarillo National Resource Center for Plutonium and Weapons Plutonium Disposition,

Belgium Nuclear Research Center, Mol, Belgium, June 25, 1996.

23. Nondestructive Assay for Safeguards of Plutonium and Mixed Oxide Fuel, Los Alamos

National Laboratory, May 7, 1996.

24. The Status of the Water-Reactor Options for Disposition of Weapons Plutonium Project,

Oak Ridge National Laboratory, Oak Ridge, TN, Apr. 17, 1996.

25. The Status of the Water-Reactor Options for Disposition of Weapons Plutonium Project,

U. S. Department of Energy, Washington, DC, Mar. 18-19, 1996.

26. Weapons Plutonium Safeguards Project at the Amarillo National Resource Center for

Plutonium, Sandia National Laboratory, Albuquerque, NM, Oct. 23, 1995.

27. Weapons Plutonium Safeguards Project at the Amarillo National Resource Center for

Plutonium, Los Alamos National Laboratory, Los Alamos, NM, Oct. 25, 1995.

11 11

28. Development of Nondestructive Assay Methods for Weapons Plutonium and MOX Fuel

Safeguards, Amarillo National Resource Center for Plutonium, Amarillo, TX, Sep. 29,

1995.

29. Measurements of U235 and Pu239 in Rensselaer Nondestructive Assay Device, Knolls

Atomic Physics Laboratory, Schenectady, NY, 1992.

30. Nondestructive Fissile Assay Measurements Using the Lead Slowing Down Time

Spectrometer, Brookhaven National Laboratory, Upton, NY 1992.