CALVIN M. HOPPER

PUBLICATIONS

2008

2007

2006

B. L. Broadhead, C. M. Hopper, and J. J. Wagschal, "Sensitivity of Adjusted Responses to Parameter and Response Uncertainties," Proceedings of PHYSOR 2006, Vancouver, BC, Canada, September 10-14, 2006.

2005

C. M. Hopper and J. J. Wagschal, "Determination of Consistent Benchmarks Used for Nuclear Criticality Safety Analysis Applications," Trans. Am. Nucl. Soc. 93, 257-259 (2005).

H. L. Dodds, C. M. Hopper, R. E. Pevey, D. A. Reed, R. G. Taylor, and R. M. Westfall, "Nuclear Criticality Safety Education and Training: Anytime and Anywhere," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005.

S. Goluoglu and C. M. Hopper, “Application of Validation Methodogies for a Generic Validation Problem,” presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005.

P. B. Fox, L. M. Petrie, Jr., and C. M. Hopper, Minimum Critical Values Study, ORNL/TM-2003/211, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2005.

J. T. Thomas, R. M. Westfall, and C. M. Hopper, "History of the Oak Ridge Critical Experiments Program," Trans. Am. Nucl. Soc. 92, 470-471 (2005).

D. Loaiza, R. Sanchez, K. Chesson, M. Westfall, and C. Hopper, "Critical Mass Experiment with Niobium - 1 wt% Zirconium Fueled with Highly Enriched Uranium in Support of Project Prometheus," Trans. Am. Nucl. Soc. 92, 580-581 (2005).

B. T. Rearden, C. M. Hopper, and K. R. Elam, "TSUNAMI Analysis of the Applicability of Proposed Experiments to Reactor-Grade and Weapons-Grade Mixed Oxide Systems," presented at the International Symposium NUCEF2005, Tokai, Japan, February 9-10, 2005.

2004

B. L. Broadhead , B. T. Rearden, C. M. Hopper, J. J. Wagschal, and C. V. Parks, “Sensitivity-and-Uncertainty-Based Criticality Safety Validation Techniques,” Nucl. Sci. Eng. 146 , 340-366 (2004).

C. M. Hopper, Report of Foreign Travel to Obninsk, Russia, March 15-19, 2004, XA 207659, April 2004.

R. M. Westfall and C. M. Hopper, Joint Report of Foreign Travel to Paris, April 9-19, 2004, XA 208273 and 208742, May 2004.

S. Goluoglu, K. R. Elam, B. T. Rearden, B. L. Broadhead, and C. M. Hopper, Sensitivity Analysis Applied to the Validation of the 10B Capture Reaction in Nuclear Fuel Casks, NUREG/CR-6845 (ORNL/TM-2004/48), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2004.

R. M. Westfall and C. M. Hopper, Joint Report of Foreign Travel to Prague, August 21-September 5, 2004, XA 214481 and XA 214448, September 2004.

C. V. Parks and C. M. Hopper, “Technical Basis for Proposed Fissile Exemption Criteria for Transport Packages,” presented at the 14 th International Symposium on the Packaging and Transportation of Radioactive Materials, Berlin, Germany, September 20-24, 2004.

C. M. Hopper, Report of Foreign Travel to Belgium, September 28-October 2, 2004, XA 216810, October 2004.

S. Goluoglu , and C. M. Hopper, “Impact of Benchmarks on Potential MOX Throughput,” 2004 American Nuclear Society Winter Meeting, Washington, DC, November 14­18, 2004.

C. M. Hopper, “Guide for Nuclear Criticality Safety in the Storage of Fissile Materials,” in Proc. of ANS 2004 Winter Meeting "Leadership Toward a Progressive, Integrated Nuclear Community–Going Forward Together," November 14–18, 2004, Washington, D.C., Trans. Am. Nucl. Soc. 91, 642-643 (November 2004).

2003

Y. Karni, D. Regev, E. Greenspan, S. Goluoglu, L. M. Petrie, and C. M. Hopper, "On theSMORES Capability for Minimum Critical Mass Determination," in Proc. of ANS 2003 Annual Meeting "The Nuclear Technology Expansion: Unlimited Opportunities," June l-5, 2003, San Diego, CA. [Summary]. Trans. Am. Nucl. Soc. 88, 82-83 (June 2003).

Sedat Goluoglu, C. M. Hopper, and B. T. Rearden, "Extended Interpretation of Sensitivity Data for Benchmark Areas of Applicability," Trans. Am. Nucl. Soc. 88, 77-79 (June 2003).

C. M. Hopper , Report of Foreign Travel to Avignon, France, June 1-12, 2003, FTR-168295, July 2003.

B. T. Rearden, C. M. Hopper, K. R. Elam, S. Goluoglu, and C. V. Parks, Applications of the TSUNAMI Sensitivity and Uncertainty Analysis Methodology,” pp. 61-66 in Proc. of The 7 th International Conference on Nuclear Criticality Safety (ICNC2003) , October 20-24, 2003, Tokai-mura, Japan.

Y. Karni, D. Regev, E. Greenspan, S. Goluoglu, L. M. Petrie, and C. M. Hopper, “The SMORES Capability for Minimum Critical Mass Determination,” in Proc. of The 7th International Conference on Nuclear Criticality Safety (ICNC2003), October 20–24, 2003, Tokai­mura, Japan.

Sedat Goluoglu, K. R. Elam, B. T. Rearden, B. L. Broadhead, C. M. Hopper, and C.V. Parks, “Validation of the 10B Capture Reaction in Nuclear Fuel Casks with Sensitivity Analysis,” in Proc. of ANS: International ANS/ENS 2003 Winter Meeting with cooperation from Nuclear Energy Institute on Nuclear Technology: Achieving Global Economic Growth While Safeguarding the Environment, November 16–20, 2003, New Orleans, Louisiana. [Summary] Trans. Am. Nucl. Soc. 89, 134–135 (2003).

C. F. Weber and C. M. Hopper , "Modeling Actinide Solution Densities with the Pitzer Method," in Proc. of American Nuclear Society: International ANS/ENS 2003 Winter Meeting with cooperation from Nuclear Energy Institute on "Nuclear Technology: Achieving Global Economic Growth While Safeguarding the Environment," November 16-20, 2003, New Orleans, Louisiana. Trans. Am. Nucl. Soc. 89, 123-124 (2003).

Sedat Goluoglu and C. M. Hopper, Assessment of Degree of Applicability of Benchmarks for Gadolinium Using KENO V.a and the 238-Group SCALE Cross-Section Library, ORNL/TM-2003/106, UT-Battelle, LLC, Oak Ridge National Laboratory, December 2003.

2002

S. Goluoglu and C. M. Hopper, DOE NCSP Review of TRUPACT-II/HalfPACT Fissile Limits, ORNL/TM-2002/58, UT-Battelle, LLC, Oak Ridge National Laboratory, March 2002.

S. Goluoglu, L. M. Petrie, and C. M. Hopper, “SMORES - A New SCALE Sequence for the Determination of Bounding Curves and Data,” Trans. Am. Nucl. Soc. 86, 114-116 (June 2002). Track 50726

C. V. Parks, B. D. Murphy, L. M. Petrie, and C. M. Hopper, Plutonium Production Using Natural Uranium From the Front-End of the Nuclear Fuel Cycle, ORNL/TM-2002/118, UT-Battelle, LLC, Oak Ridge National Laboratory, September 2002.

R. M. Westfall and C. M. Hopper, Joint Report of Foreign Travel to Paris, France, September 9‑17, 2002 (Westfall) and September 7-12, 2002 (Hopper), TA#161437, TA#161386, October 14, 2002.

C. M. Hopper , L. M. Petrie, L. J. Ott, and C. V. Parks, Design Parameters for a Natural Uranium UO 3- or U 3O 8-Fueled Nuclear Reactor, ORNL/TM-2002/240, UT-Battelle, LLC, Oak Ridge National Laboratory, November 2002.

2001

C. M. Hopper , Report of Foreign Travel to Sellafield, United Kingdom, April 24-28, 2001, FTR 135639 (May 2001).

C. M. Hopper , L. M. Petrie, and D. F. Hollenbach, Results and Interpretations for Establishing Criticality Indexes for Material Handling and Storage Configurations, ORNL/CF-01/28, Oak Ridge National Laboratory, May 2001 (Letter Report to M. Brady Raap).

J. T. Thomas and C. M. Hopper, Critical Experiments With Aqueous Solutions of 233UO 2(NO 3) 2, ORNL/TM-2000/245, UT-Battelle, LLC, Oak Ridge National Laboratory, May 2001.

K. E. Elam, C. M. Hopper, C. V. Parks, and T. E. Harris, Emplacement Guidance for Criticality Safety in Low-Level-Waste Disposal, ORNL/TM-13765, UT-Battelle, LLC, Oak Ridge National Laboratory, June 2001.

S. Goluoglu and C. M. Hopper (Evaluators), Evaluation of Critical Experiments With Aqueous Solutions of 233 UO 2 (NO 3 ) 2 , NEA/NSC/DOC/(95)03/V, Volume V, U233-SOL-THERM-006, published by Nuclear Energy Agency, Paris, France.

B. L. Broadhead, C. M. Hopper, R. L. Childs, J. J. Wagschal, and C. V. Parks, “Sensitivity and Uncertainty-Based Criticality Safety Validation Techniques,” Nucl. Sci. Eng . , in preparation.

C. M. Hopper , “The U.S. Nuclear Criticality Safety Experience, Needs, and Future in a Global Economy,” in Proc. of NUCEF 2001 (Nuclear Fuel Cycle Safety Engineering Research Facility) International Symposium, Scientific Basis for Criticality Safety, Separation Process and Waste Disposal, October 31 - November 2, 2001, Tokai-mura, Japan (2001).

2000

C. V. Parks, B. T. Rearden, M. D. DeHart, B. L. Broadhead, C. M. Hopper, and L. M. Petrie, "Annual Environmental Management Science Program (EMSP) Project Summary. Project Title: Development of Nuclear Analysis Capabilities for DOE Waste Management Activities," ORNL/TM-2000/65, February 2000.

C. M. Hopper, Report of Foreign Travel to Tokyo, Japan, May 8-14, 2000, XA118903, May 2000.

T. E. Valentine, K. R. Elam, and C. M. Hopper, Joint Report of Foreign Travel to St. Petersburg, Moscow, and Obninsk, Russia, June 23-July 1, 2000, ORNL/FTR-XA 119334, July 26, 2000.

B. L. Broadhead, C. M. Hopper, S. C. Frankle, J. F. Briesmeister, R. C. Little, and J. J. Wagschal, Further Investigations of NIST Water Sphere Discrepancies, ORNL/TM-2000/173, UT-Battelle, LLC, Oak Ridge National Laboratory, October 2000.

Y. Shimizu and C. M. Hopper, Computation Results from a Parametric Study to Determine Bounding Critical Systems of Homogeneously Water-Moderated Mixed-Plutonium-Uranium Oxides , ORNL/TM-2000/151, October 2000.

C. M. Hopper, “A Tool for Criticality Accident Emergency Planning, Training and Response,” pp. 000-000 in Proc. International Workshop on the Safety of the Nuclear Fuel Cycle, May 29-31, 2000, Science Museum, Tokyo, Japan.

C. M. Hopper, “The Value of and Need for International Nuclear Criticality Safety Standards--A Report on ISO TC 85/SC 5/WG 8 Activities,” pp. 000-000 in Proc. International Workshop on the Safety of the Nuclear Fuel Cycle, May 29-31, 2000, Science Museum, Tokyo, Japan.

B. L. Broadhead, R. L. Childs, and C. M. Hopper, “Illustrative Examples of Least-Squares Methods for Criticality Safety,” Proc. of ANS/ENS 2000 International Winter Meeting and Embedded Topical Meetings, November 12-16, 2000, Washington, D.C. Trans. Am. Nucl. Soc. 83, 100-103, 2000.

B. L. Broadhead, C. M. Hopper, K. R. Elam, B. T. Rearden, and R. L. Childs, “Criticality Safety Applications of S/U Validation Methods,” Proc. of ANS/ENS 2000 International Winter Meeting and Embedded Topical Meetings, November 12-16, 2000, Washington, D.C. Trans. Am. Nucl. Soc. 83, 107-113, 2000.

C. M. Hopper, “Guide for Nuclear Criticality Safety in the Storage of Fissile Materials,” American Nuclear Society ANS/ENS 2000 International Winter Meeting and Embedded Topical Meetings, November 12-16, 2000, Washington, D.C. Trans. Am. Nucl. Soc. 83, 151-152, 2000.

C. M. Hopper , “Overview of Sensitivity and Uncertainty Analysis Methods for Establishing Areas of Applicability and Subcritical Margins,” American Nuclear Society ANS/ENS 2000 International Winter Meeting and Embedded Topical Meetings, November 12-16, 2000, Washington, D.C. Trans. Am. Nucl. Soc. 83, 90-93, 2000.

B. T. Rearden, C. M. Hopper, K. R. Elam, B. L. Broadhead, and P. B. Fox, “Prototypic Applications of Sensitivity and Uncertainty Analysis for Experiment Needs,” Proc. of ANS/ENS 2000 International Winter Meeting and Embedded Topical Meetings, November 12‑16, 2000, Washington, D.C. Trans. Am. Nucl. Soc. 83, 103-107, 2000.

1999

C. M. Hopper and K. R. Elam, Proposed Outline for Guidance Documentation Emplacement Criticality Guidance for Low-Level Waste Disposal, ORNL/M-6637, U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 1999. Task 4 Milestone.

B. L. Broadhead, C. M. Hopper, and C. V. Parks, “ Application of Covariance Data to Criticality Safety Data Validation,” presented at the Covariance Workshop, Brookhaven National Laboratory, April 22–23, 1999.

C. V. Parks, B. T. Rearden, M. D. DeHart, B. L. Broadhead, C. M. Hopper, and L. M. Petrie," Annual Environmental Management Science Program (EMSP) Summary Progress Report. Project Title: Development of Nuclear Analysis Capabilities for DOE Waste Management Activities," ORNL/TM-1999/101, June 1999.

American Nuclear Society, 1999 Annual Meeting, Boston, Massachusetts, June 6-10, 1999. DOE’s Nuclear Criticality Safety Program, DNFSB 97-2, Panel Discussion/Round Table participants (pg. 157): C. M. Hopper, Applicable Ranges.

L. E. Toran, C. M. Hopper, C. V. Parks, and V. A. Colten-Bradley, “The Potential for Criticality Following Disposal of Uranium at Low-Level Waste Facilities, Volume 2: Containerized Disposal,” NUREG/CR-6505, Vol. 2 (ORNL/TM-13323/V2), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., June 1999.

C. M. Hopper , B. L. Broadhead, R. L. Childs, and C. V. Parks, "Slide Rule for Rapid Response Estimation of Radiological Dose from Criticality Accidents," pp. 1334-1344 in Proceedings of ICNC'99, Sixth International Conference on Nuclear Criticality Safety, Vol. III, Palais des Congrès, Versailles, FRANCE, September 20-24, 1999. Oral Presentation. [Paper]

C. M. Hopper , K. R. Elam, C. V. Parks, and J. J. Lichtenwalter, "Bounding Values for Low-Level-Waste Transport Exemptions and Disposal," pp. 438-446 in Proceedings of ICNC'99, Sixth International Conference on Nuclear Criticality Safety, Vol. I, Palais des Congrès, Versailles, FRANCE, September 20-24, 1999. Poster Presentation. [Paper]

B. L. Broadhead, C. M. Hopper, and C. V. Parks, "Proposed Methodology for Establishing Area of Applicability," pp. 787-798 in Proceedings of ICNC'99, Sixth International Conference on Nuclear Criticality Safety, Vol. II, Palais des Congrès, Versailles, FRANCE, September 20-24, 1999. [Paper]

C. M. Hopper , Report of Foreign Travel to Versailles, France, September 25-29, 1999, XA 108355 (October 1999).

B. L. Broadhead, C. M. Hopper, and C. V. Parks, “Sensitivity and Uncertainty Analysis Applied to Range of Applicability Determination,” Trans. Am. Nucl. Soc. 81, 172-174 (1999). American Nuclear Society 1999 Winter Meeting, Long Beach, California, November 14- 18, 1999.

C. W. Forsberg, C. M. Hopper, and H. C. Vantine, “What Is Nonweapons-Usable 233U?” Trans. Am. Nucl. Soc. 81, 62-63 (1999). American Nuclear Society 1999 Winter Meeting, Long Beach, California, November 14- 18, 1999.

C. W. Forsberg, K. R. Elam, C. M. Hopper, “Respository Criticality Control for 233 U Using Depleted Uranium,” Trans. Am. Nucl. Soc. 81, 166-167 (1999). American Nuclear Society 1999 Winter Meeting, Long Beach, California, November 14- 18, 1999.

B. L. Broadhead, C. M. Hopper, R. L. Childs, and C. V. Parks, Sensitivity and Uncertainty Analyses Applied to Criticality Safety Validation, Volume 1: Methods Development,” NUREG/CR-6655, Vol. 1 (ORNL/TM-13692/V1), prepared for the U.S. Nuclear Regulatory Commission by
Oak Ridge National Laboratory, Oak Ridge, Tenn., November 1999.

B. L. Broadhead, C. M. Hopper, and C. V. Parks, Sensitivity and Uncertainty Analyses Applied to Criticality Safety Validation, Volume 2: Illustrative Applications and Initial Guidance,” NUREG/CR-6655, Vol. 2 (ORNL/TM-13692/V2), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., November 1999.

1998

C. M. Hopper, Report of Foreign Travel to Paris, France, March 23-27, 1998, ORNL/FTR-6521, April 1998.

C. W. Forsberg, C. M. Hopper, J. L. Richter, and H. C. Vantine, Definition of Weapons-Usable Uranium-233, ORNL/TM-13517, March 1998.

B. L. Broadhead, R. L. Childs, C. M. Hopper, and C. V. Parks, “Dose Consequences from a Postulated Criticality Occurring in a Low-Level-Waste Disposal Facility,” pp. I-390-I-395 in

Proceedings of the 1998 ANS Radiation Protection and Shielding Division Topical Conference on Technologies for the New Century , Vol. 1, Nashville, Tenn., April 19-23, 1998.

C. V. Parks, C. M. Hopper, J. J. Lichtenwalter, E. P. Easton, and P. G. Brochman, “Assessment of the U.S. Regulations for Fissile Exemptions and Fissile Material General Licenses,” pp. 1098-1106 in Proceedings of PATRAM 98 The 12 th International Conference on the Packaging and Transportation of Radioactive Materials , Vol. 3, Paris, France, May 10-15, 1998.

C. M. Hopper , and B. L. Broadhead, An Updated Nuclear Criticality Slide Rule. Volume 2: Functional Slide Rule, NUREG/CR-6504, Vol. 2 (ORNL/TM-13322/V2), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., April 1998.

C. V. Parks, C. M. Hopper, and J. L. Lichtenwalter, Assessment and Recommendations for Fissile-Material Packaging Exemptions and General Licenses Within 10 CFR Part 71, NUREG/CR-5342 (ORNL/TM-13607), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., July 1998.

C. V. Parks, M. D. DeHart, B. L. Broadhead, C. M. Hopper, L. M. Petrie, “Development of Nuclear Analysis Capabilities for DOE Waste Management Activities,” pp. 222-223 in Proceedings of Environmental Management Science Program Workshop, Chicago, Illinois, July 27-30, 1998, CONF-980736, July 1998 (Poster 113).

B. T. Rearden, J. J. Lichtenwalter, and C. M. Hopper, “Evaluation of Critical Experiment Parameters and Uncertainties With First-Order Sensitivity Techniques,” NUREG/CR-5624 (ORNL/TM-13718), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., December 1998. DRAFT REPORT. Task 1 for JCN W6479.

C. M. Hopper , “Candidate Methodologies for Criticality Safety LLW Emplacement Guidance,” ORNL/M-6617 (Letter Report to T. E. Harris) (November 1998).

1997

J. J. Lichtenwalter, S. M. Bowman, M. D. DeHart, and C. M. Hopper, Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages, NUREG/CR-6361 (ORNL/TM-13211), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., March 1997.

B. L. Broadhead, C. M. Hopper, R. L. Childs, and J. S. Tang, An Updated Nuclear Criticality Slide Rule. Volume 1: Technical Basis, NUREG/CR-6504, Vol. 1 (ORNL/TM-13322/V1), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., April 1997.

L. E. Toran, C. M. Hopper, M. T. Naney, C. V. Parks, J. F. McCarthy, B. L. Broadhead, and V. A. Colten-Bradley, The Potential for Criticality Following Disposal of Uranium at Low-Level Waste Facilities. Volume 1: Uranium Blended with Soil, NUREG/CR-6505, Vol. 1 (ORNL/TM-13323/V1), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., June 1997.

E. S. Glouchkov, C. M. Hopper, W. C. Jordan, and R. G. Taylor, Report of Foreign Travel to Japan, ORNL/FTR-6249, July 29, 1997.

D. F. Hollenbach and C. M. Hopper, “Criticality Safety Considerations for MSRE Fuel Drain Tank Uranium Aggregation, pp. 23-30 in Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, Chelan, WA, September 7-12, 1997.

C. M. Hopper and C. V. Parks, “Potential for and Consequences of Criticality Resulting from Hydrogeochemically Concentrated Fissile Uranium Blended with Soil in Low-Level Waste Disposal Facilities,” pp. 73-79 in Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, Chelan, WA, September 7-12, 1997.

C. M. Hopper , R.Q. Wright, K.R. Elam, and C.W. Forsberg, “Isotopic Dilution of 233U with Depleted Uranium for Criticality Safety in Processing and Disposal,” pp. 176-180 in Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, Chelan, WA, September 7‑12, 1997.

K. R. Elam, C. W. Forsberg, C. M. Hopper, R. Q. Wright, Isotopic Dilution Requirements for 233U Criticality Safety in Processing and Disposal Facilities, ORNL/TM-13524, November 1997.

1996

B. L. Broadhead, R. L. Childs, J. S. Tang, and C. M. Hopper, Verification of Criticality Accident Alarm System for Molten Salt Reactor Remediation Activities, ORNL/CF-95/99, January 1996.

D. E. Mueller, C. M. Hopper, and E. C. Crume, Jr., “Molten Salt Reactor Experiment Remediation,” Nuclear Criticality Technology Safety Project, Gaithersburg, MD, May 14-15, 1996.

C. M. Hopper , Report of Foreign Travel to Russia, January 31-February 7, 1996, ORNL/FTR‑5726, March 1996..

D. F. Hollenbach and C. M. Hopper, Criticality Safety Study of the MSRE Auxiliary Charcoal Bed, ORNL/M-5450, September 1996.

1995

C. M. Hopper , “Criticality Safety Considerations for Low-Level Waste Facilities,” Trans. Am. Nucl. Soc. 72, 184-85 (1995).

B. L. Broadhead and C. M. Hopper, “Updated Tool for Nuclear Criticality Accident Emergency Response,” Trans. Am. Nucl. Soc. 72, 218-20 (1995).

C. M. Hopper , R. H. Odegaarden, C. V. Parks and P. B. Fox, Criticality Safety Criteria for License Review of Low-Level-Waste Facilities, NUREG/CR-6284 (ORNL/TM-12845), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., 1995.

B. L. Broadhead, R. L. Childs, and C. M. Hopper, “Verification of Criticality Accident Alarm System for Environmental Restoration Activities,” presented at ICNC ‘95 Fifth International Conference on Nuclear Criticality Safety, Albuquerque, NM, September 17-21, 1995.

C. M. Hopper , W. C. Jordan, and D. F. Hollenbach, “Calculated Neutron Spectra for Heterogeneous U(93) and CH 2 Critical Assemblies,” Trans. Am. Nucl. Soc. 73, 220-22 (1995).

Calvin M. Hopper, “Elements of a Nuclear Criticality Safety Program,” Nucl. Safety 36(2), 234-242 (1995).

1994

D. F. Hollenbach and C. M.Hopper, “Criticality Safety Study of the MSRE Fuel Drain Tank Cell,” Trans. Am. Nucl. Soc. 70, 213-15 (1994).

A. Wilkinson, B. Basoglu, C. Bentley, M. Dunn, M. Plaster, T. Yamamoto, H. Dodds, and C. Hopper, “Improved Dose Estimates for Nuclear Criticality Accidents: Preliminary Results,” Trans. Am. Nucl. Soc. 70, 191-2 (1994).

H. L. Dodds, C. M. Hopper, J. T. Mihalczo, J. T. Thomas, and R. M. Westfall, “Nuclear Criticality Safety Courses at the University of Tennessee-Knoxville,” Trans. Am. Nucl. Soc. 70, 34-35 (1994).

D. F. Hollenbach and C. M. Hopper, Criticality Safety Study of the MSRE Fuel Drain Tank Cell in Building 7503, ORNL/TM-12642, 1994.

C. M. Hopper , “Department of Energy Plutonium ES&H Vulnerability Assessment Oak Ridge Site Assessment Team Report,” 1994.

C. M. Hopper , “DOE Spent Nuclear Fuel—Nuclear Criticality Safety Challenges and Safeguards Initiatives,” Proc. Am. Nucl. Soc. Top. Mtg. on DOE Spent Nuclear Fuel Challenges and Initiatives, Salt Lake City, UT, December 13-16, 1994.

1993

C. M. Hopper , “Nuclear Criticality Safety Specialist Training and Qualification Programs,” Trans. Am. Nucl. Soc. 69, 255-56 (1993).

1992

R. T. Primm, C. M. Hopper, and G. R. Smolen, Criticality Safety Studies for the Storage of Waste from Nuclear Fuel Services in Intercell Storage Wells 2 and 3 of Building 3019, ORNL/TM-12152 (1992).

1991

C. M. Hopper , “ANSI/ANS-8.7-1982(R88) Guide for Nuclear Criticality Safety in the Storage of Fissile Materials,” Trans. Am. Nucl. Soc. 64, 330 (1991).

G. A. Aramayo, C. M. Hopper, J. R. Kirkpatrick, D. M. McGinty, J. T. Muecke, and J. C. Walls, Safety Analysis Report for Packaging: The ORNL HFIR Unirradiated Fuel Element Shipping Container, Vol. 1, ORNL/TM-11656/V1 (1991).

G. A. Aramayo, C. M. Hopper, J. R. Kirkpatrick, D. M. McGinty, J. T. Muecke, and J. C. Walls, Safety Analysis Report for Packaging: The ORNL HFIR Unirradiated Fuel Element Shipping Container, Vol. 2, ORNL/TM-11656/V2 (1991).

1990

C. M. Hopper and J. P. Renier, “Expanded and Applied Sixteen Neutron-Energy-Group Cross-Section Library,” Trans. Am. Nucl. Soc. 61, 186-88 (1990).

1987

R. W. Barber, B. P. Brown, and C. M. Hopper, “The United States Department of Energy Office of Nuclear Safety National Criticality Safety Program and Activities,” Int. Seminar on Nuclear Criticality Safety, Tokyo, Oct. 19-23, 1987.

1986

C. M. Hopper , “U.S. DOT Specification 6M Radioactive Fissile Material Package Nuclear Criticality Safety Re-Evaluation,” IAEA Int. Symp. Packaging and Transport of Radioactive Materials, Davos, Switzerland, June 16-20, 1986, IAEA-SM-286/222, 1987.

1985

C. M. Hopper , “Economics of the Specification 6M Safety Re-Evaluation and Regulatory Requirements,” Trans. Am. Nucl. Soc. 50, 311-13 (1985).

R. W. Barber, B. P. Brown, and C. M. Hopper, “Overview of DOE/ONS Criticality Safety Projects,” Trans. Am. Nucl. Soc. Jackson, WY, Sept. 9-11, 1985.

1974

G. R. Handley and C. M. Hopper, Validation of the “KENO” Code for Nuclear Criticality Safety Calculations of Moderated, Low-Enriched Uranium Systems, Y-1948, June 1974.