Burnup Credit-Related Publications

The following is a list of nearly 200 publications that are either directly or indirectly related to burnup credit and criticality safety for spent nuclear fuel. The list will hopefully provide a useful resource of previous works to those working in burnup credit. The list was compiled by the staff of the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory (ORNL) as a byproduct of several burnup credit research projects. While extensive, the list is not exhaustive. It is our intention to expand and maintain the list as additional relevant publications come to our attention. Suggestions for additions and/or modifications are welcome and should be directed to John C. Wagner. Finally, note that the presence or absence of a publication in this list should not be construed as an indication of approval or disapproval of the quality or technical merit of the publication.

Author(s) / Report Title / Publication Number / Date

2012

J. M. Scaglione, D. E. Mueller, J. C. Wagner, and W. J. Marshall, An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff) Predictions, NUREG/CR-7109 (ORNL/TM-2011/514), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2012.

G. Radulescu, I. C. Gauld, G. Ilas, and J. C. Wagner, An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predictions, NUREG/CR-7108 (ORNL/TM-2011/509), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2012.

Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation, Electric Power Research Institute, Palo Alto, CA: April 2012. 1025203.

G. Radulescu and J. C. Wagner, Burn-up Credit Criticality Safety Benchmark - Phase VII, UO₂ Fuel: Study of Spent Fuel Compositions for Long-term Disposal, A Report by the Expert Group on Burn-up Credit Criticality NEA Nuclear Science Committee, Working Party on Nuclear Criticality Safety, ISBN 978-92-64-99172-9, NEA No. 6998, Nuclear Energy Agency, Organisation for Economic Co-operation and Development, February 2012.

2011

Burnup Credit-Contribution to the Analysis of the Yankee Rowe Radiochemical Assays, Electric Power Research Institute, Palo Alto, CA: October 2011. 1022910.

L. Jutier, I. Ortiz de Echevarria, S. Evo et al., "Latest Studies Related to the Use of Burnup Credit in France," Proceedings of ICNC 2011, Edinburgh, Scotland, September 19-23, 2011.

I. Ortiz de Echevarria, L. Jutier and A. Gallozzi, "Conservatisms of Irradiation Conditions in Burnup Credit Implementation for PWR Fuel," Proceedings of ICNC 2011, Edinburgh, Scotland, September 19-23, 2011.

G. Radulescu, I. C. Gauld, G. Ilas, and J. C. Wagner, "An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Isotopic Composition Predictions," Proceedings of ICNC 2011, Edinburgh, Scotland, September 19-23, 2011.

J. M. Scaglione, D. E. Mueller, and J. C. Wagner, "An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Criticality (k_eff) Predictions," Proceedings of ICNC 2011, Edinburgh, Scotland, September 19-23, 2011.

Benchmarks for Quantifying Fuel Reactivity DepletionUncertainty, Electric Power Research Institute, Palo Alto, CA: August 2011. 1022909.

G. Radulescu and J. C. Wagner, "Review of Results for the OECD/NEA Phase VII Benchmark: Study of Spent Fuel Compositions for Long-Term Disposal," Proceedings of the 13th International High-Level Radioactive Waste Management Conference (IHLRWMC), Albuquerque, NM, April 10-14, 2011.

J. M. Scaglione and J. C. Wagner, "Review of Yucca Mountain Disposal Criticality Studies," Proceedings of the 13th International High-Level Radioactive Waste Management Conference (IHLRWMC), Albuquerque, NM, April 10-14, 2011.

2010

C. V. Parks, J. C. Wagner, D. E. Mueller, and I. C. Gauld, "Development of Technical Basis for Burnup Credit Regulatory Guidance in the United States," PATRAM 2010, London, U.K., October 3-8, 2010.

G. Ilas, I. C. Gauld, F. C. Difilippo, and M. B. Emmett, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation--Calvert Cliffs, Takahama, and Three Mile Island Reactors, NUREG/CR-6968 (ORNL/TM-2008/071), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2010.

G. Ilas, I. C. Gauld, and B. D. Murphy, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation--ARIANE and REBUS Programs UO₂ Fuel), NUREG/CR-6969 (ORNL/TM-2008/072), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2010.

2009

B. B. Bevard, J. C. Wagner, C. V. Parks, and M. Aissa, Review of Information for Spent Nuclear Fuel Burnup Confirmation, NUREG/CR-6998, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2009.

J. M. Scaglione and J. C. Wagner, "Burnup Credit Approach for the Proposed United States Repository at Yucca Mountain," Proceedings of the IAEA/CSN International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Cordoba, Spain, October 27-30, 2009.

L. Jutier, M. Clergeau, L. Aguiar and I. Ortiz de Echevarria, "Investigation of Burnup Credit Implementation for BWR Fuel," Proceedings of NCSD 2009, Richland, USA, September 13-17, 2009.

T. Ivanova, N. Leclerc and E. Letang, "Use of Fission Product Experiments for Burnup Credit Validation," Proceedings of NCSD 2009, Richland, USA, September 13-17, 2009.

F. Fernex, T. Ivanova, F. Bernard, and E. Letang, "HTC Experimental Program: Validation and Calculational Analysis," Nucl. Sci. Eng. 162, 1-24 (2009).

N. Leclaire, T. Ivanova, E. Letang, E. Girault, and J-F. Thro, "Fission Product Experimental Program: Validation and Computational Analysis," Nucl. Sci. Eng. 161, 188-215 (2009).

G. Radulescu, D. E. Mueller, and J. C. Wagner, "Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit," Nucl. Technol. 167(2), 268-287, August 2009.

2008

"Burnup Credit for LWR Fuel," ANSI/ANS-8.27-2008, an American National Standard, published by the American Nuclear Society, LaGrange Park, IL, 2008.

A. H. Wells, Feasibility of Direct Disposal of Dual-Purpose Canisters, Options for Assuring Critical Control, 1016629, Final Report, Electric Power Research Institute, Palo Alto, CA, December 2008.

L. Jutier, B. Checiak, J. Raby, L. Aguiar and I. Le Bars, "Conservative Approach for PWR MOX Burnup Credit Implementation," Proceedings of PHYSOR 2008, Interlaken, Switzerland, September 14-19, 2008.

D. E. Mueller, K. R. Elam, and P. B. Fox, Evaluation of the French Haut Taux de Combustion (HTC) Critical Experiment Data, NUREG/CR-6979 (ORNL/TM-2007/083), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2008.

J. C. Wagner, Criticality Analysis of Assembly Misload in a PWR Burnup Credit Cask, NUREG/CR-6955 (ORNL/TM-2004/52), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2008.

G. Radulescu, D. E. Mueller, and J.C. Wagner, Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit, NUREG/CR-6951 (ORNL/TM-2006/87), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2008.

2007

"Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition," Proceedings of a Technical Meeting held in London, 29 August-2 September 2005, IAEA-TECDOC-1547, International Atomic Energy Agency (May 2007).

C. J. Dean, P. J. Smith, and R. J. Perry, "Validation of Important Fission Product Evaluations through CERES Integral Benchmarks," Proceedings of the International Conference on Nuclear Data for Science and Technology 2007, DOI: 10.1051/ndata:07172.

G. Radulescu, D. E. Mueller, S. Goluoglu, D. F. Hollenbach, and P. B. Fox, Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel, ORNL/TM-2007/127, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2007.

L. C. Leal, H. Derrien, M. E. Dunn, and D. E. Mueller, Assessment of Fission Product Cross-Section Data for Burnup Credit Applications, ORNL/TM-2005/65, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2007.

J. Raby, C. Lavarenne and F. Jean, "Bounding Plutonium Vectors for PWR-MOX Burnup Credit Applications," Proceedings of ICNC 2007, St. Petersburg, Russia, May 28-June 1, 2007.

J. Raby, B. Faivre, Y. Richet and C. Lavarenne, "Determination of Correction Factors for the Isotopic Composition in Burnup Credit Applications Taking into Account the Depletion Codes Validation," Proceedings of ICNC 2007, St. Petersburg, Russia, May 28 - June 1, 2007.

G. Radulescu, D. E. Mueller, and J. C. Wagner, "Evaluation of Applicability of CRC Models for Burnup Credit Validation," Trans. Am. Nucl. Soc. 97, 151-153 (2007).

C. V. Parks, J. C. Wagner, D. E. Mueller, and I. C. Gauld, "Full Burnup Credit in Transport and Storage Casks--Benefits and Implementation," Radwaste Solutions 14(2), 32-41 (March/April 2007).

A. Santamarina, "From Integral Experiments to Nuclear Data Improvement," Proceedings of the International Conference on Nuclear Data for Science and Technology 2007, DOI: 10.1051/ndata:07723.

2006

C. V. Parks, J. C. Wagner, and D. E. Mueller, "Full Burnup Credit in Transport and Storage Casks: Benefits and Implementation," Proc. of the International High-Level Radioactive Waste Management Conference, Las Vegas, NV, April 30-May 4, 2006, pp. 1299-1308.

M. T. Wenner, J. C. Wagner, and L. M. Petrie, "A New Source Initialization Capability for the SCALE Burnup Credit Sequence," Trans. Am. Nucl. Soc. 95, 310-311 (2006).

2005

M. D. DeHart and S. M. Bowman, "Improved Radiochemical Assay Analyses Using TRITON Depletion Sequences in SCALE," presented at the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, U.K., August 29-September 2, 2005.

I. C. Gauld and D. E. Mueller, Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations, ORNL/TM-2005/48, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2005.

D. E. Mueller and B. T. Rearden, "Sensitivity Coefficient Generation for a Burnup Credit Cask Model using TSUNAMI-3D," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005.

D. E. Mueller and J. C. Wagner, "Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation," presented at the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, U.K., August 29-September 2, 2005.

C. V. Parks and J. C. Wagner, "A Coordinated U.S. Program to Address Full Burnup Credit in Transport and Storage Casks," presented at the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, U.K., August 29-September 2, 2005.

C. V. Parks, C. J. Withee, and J. C. Wagner, "U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks," presented at the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, U.K., August 29-September 2, 2005.

J. C. Wagner and D. E. Mueller, "Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs," presented at the 2005 NCSD Topical Meeting, Knoxville, TN, September 19-22, 2005.

J. C. Wagner, C. V. Parks, and D. E. Mueller, "Assessment of Benefits for Extending Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA," presented at the IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, U.K., August 29-September 2, 2005.

A. Zimmer, J. Razvi, L. Johnson, B. Welch, and D. Lancaster, "Expansion of the Capabilities of the GA-4 Legal Weight Truck Spent Fuel Shipping Cask," RAMTRANS 16(3), 205-209 (2005).

2004

BSC (Bechtel SAIC Company) 2004a. BWR Axial Profile. CAL-DSU-NU-000005 REV 00A. Las Vegas, Nevada: Bechtel SAIC Company. ACC: DOC.20040927.0039.

BSC (Bechtel SAIC Company) 2004b. 21-PWR Waste Package with Absorber Plates Loading Curve Evaluation. Las Vegas, Nevada: Bechtel SAIC Company. ACC: DOC.20040922.0004.

G. A. Harms, P. H. Helmick, J. T. Ford, S. A. Walker, D. T. Berry, and P. S. Pickard, Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel, Final Report, Nuclear Energy Research Initiative Project 99-0200, Sandia Report SAND2004-0912, Sandia National Laboratories, April 2004.

H. L. Massie, Jr. 2004. Reactor Record Uncertainty Determination. 32-5041666-02. Las Vegas, Nevada: Areva. ACC: DOC.20040623.0002.

C. V. Parks and J. C. Wagner, "Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation," Proc. Of American Nuclear Society, 14^th Pacific Basin Conf., Honolulu, Hawaii, March 21-25, 2004.

C. V. Parks and J. C. Wagner, "Status of Burnup Credit for Transport of SNF in the United States," 14th International Symposium on the Packaging and Transportation of Radioactive Materials, Berlin, Germany, September 20-24, 2004.

2003

BSC (Bechtel SAIC Company) 2003a. PWR Axial Burnup Profile Analysis. CAL-DSU-NU-000012 REV 00A. Las Vegas, Nevada: Bechtel SAIC Company. ACC: DOC.20031002.002.

BSC (Bechtel SAIC Company) 2003b. Commercial Spent Nuclear Fuel Waste Package Misload Analysis. CAL-WHS-MD-000003 REV 00A. Las Vegas, Nevada: Bechtel SAIC Company. ACC: DOC.20031002.0005.

Burnup Credit—Technical Basis for Spent-Fuel Burnup Verification, Electric Power Research Institute, Palo Alto, CA: 2003. 1003418

J. Raby, C. Lavarenne et al., "Current Studies Related to the Use of Burnup Credit in France," Proceedings of ICNC 2003, Tokai, Japan, October 20-24, 2003.

I. C. Gauld, Strategies for Application of Isotopic Uncertainties in Burnup Credit, NUREG/CR-6811 (ORNL/TM-2001/257), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2003.

D. B. Lancaster, "Effect of Additional Chemical Assay Data on Actinide-Only Burnup Credit," Trans. Am. Nucl. Soc. 88, 524-526 (2003).

C. V. Parks and C. J. Withee, "Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit," pp. 500-507 in Proc. of American Nuclear Society 2003 10th International High-Level Radioactive Waste Management (IHLRWM) Conference, "Progress Through Cooperation," March 30 - April 2, 2003, Las Vegas, NV (2003).

C. E. Sanders and I. C. Gauld, Isotopic Analysis of High-Burnup PWR Spent Fuel Samples From the Takahama-3 Reactor, NUREG/CR-6798 (ORNL/TM-2001/259), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2003.

J. C. Wagner and C. V. Parks, Recommendations on the Credit for Cooling Time in PWR Burnup Credit Analyses, NUREG/CR-6781 (ORNL/TM-2001/272), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2003.

J. C. Wagner, M. D. DeHart, and C. V. Parks, Recommendations for Addressing Axial Burnup in PWR Burnup Credit Analyses, NUREG/CR-6801 (ORNL/TM-2001/273), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2003.

J. C. Wagner and C. E. Sanders, Assessment of Reactivity Margins and Loading Curves for PWR Burnup Credit Cask Analyses, NUREG/CR-6800 (ORNL/TM-2002/6), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2003.

J. C. Wagner, "Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs," pp. 684-689 in Proc. of The 7th International Conference on Nuclear Criticality Safety (ICNC2003), October 20-24, 2003, Tokai-mura, Japan.

J. C. Wagner, "Impact of Soluble Boron Modeling for PWR Burnup Credit Criticality Safety Analyses," 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," New Orleans, Louisiana, November 16-20, 2003, Trans. Am. Nucl. Soc. 89, 120-122 (2003).

A. H. Wells and J. M. Scaglione, "Burnup Credit Isotopic Validation with Commercial Reactor Criticals," Trans. Am. Nucl. Soc. 88, 181-182 (2003).

2002

A. S. Chesterman, "Spent Fuel Measurements to Improve Storage and Transport Efficiency," in Proc. KAIF Meeting, Spent Fuel Management, 2002, South Korea.

Fission Product Benchmarking for Burnup Credit Applications: Progress Report, Electric Power Research Institute, Palo Alto, CA: December 2002. 1002879.

Japan Atomic Energy Research Institute (JAERI), Technical Development on Burn-up Credit for Spent LWR Fuel, (Eds.) Y. Nakahara, K. Suyama, and T. Suzaki, JAERI-Tech 2000-071, Tokai-mura, Naka-gun, Ibaraki-ken, Japan, October 2000. [ORNL/TR-2001/01 English Translation, Oak Ridge National Laboratory, January 2002]

Japan Atomic Energy Research Institute (JAERI), OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport, (Eds.) H. Okuno, Y. Naito, and K. Suyama, JAERI-Research 2002-001, NEA/NSC/DOC(2002)2, JAERI, February 2002.

D. Lancaster, "PWR Burnup Credit Using Both Belts and Suspenders," Trans. Am. Nucl. Soc. 86, 102-03 (2002).

A. LeBrun et al., "Cross-Checking of the Operator Data Used for Burn Up Measurements," in Proc. of the International Atomic Energy Agency (IAEA) Technical Committee Meeting on Requirements, Practices, and Developments in Burnup Credit Applications, April 22-26, 2002, Madrid, Spain.

NRC (U.S. Nuclear Regulatory Commission). 2002a. Integrated Issue Resolution Status Report. NUREG-1762, Rev. 0. Washington, D.C.: U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards. ACC: MOL.20021010.0296.

C. V. Parks et al., "Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks," in Proc. of The International Atomic Energy Agency (IAEA) Technical Committee Meeting on Requirements, Practices, and Developments in Burnup Credit Applications, April 22-26, 2002, Madrid, Spain.

C. E. Sanders and J. C. Wagner, Parametric Study of the Effect of Control Rods for PWR Burnup Credit, NUREG/CR-6759 (ORNL/TM-2001/69), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2002.

C. E. Sanders and J. C. Wagner, Study of the Effect of Integral Burnable Absorbers for PWR Burnup Credit, NUREG/CR-6760 (ORNL/TM-2000/321), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2002.

C. E. Sanders and M. D. DeHart, "Computational Benchmark of the 2-D Depletion Sequence SAS2D for Characterization of Spent Nuclear Fuel," in Proc. of the International Youth Nuclear Congress (IYNC 2002), April 16-20, 2002, Daejeon, Korea.

C. E. Sanders and M. D. DeHart, "Computational Benchmark of SAS2D Against Spent Fuel Samples From the Takahama-3 Reactor," in Proc. of American Nuclear Society, 2002 Annual Meeting "The Revival of the Nuclear Energy Option", June 9-13, 2002, Hollywood, FL. Trans. Am. Nucl. Soc. 86, 100-102 (June 2002).

C. E. Sanders and John C. Wagner, "Investigation of Average and Pin-Wise Burnup Modeling of PWR Fuel," in Proc. of American Nuclear Society, 2002 Annual Meeting "The Revival of the Nuclear Energy Option", June 9-13, 2002, Hollywood, FL. Trans. Am. Nucl. Soc. 86, 98-100 (June 2002).

Spent Fuel Project Office, Interim Staff Guidance - 8, Rev. 2, Issue: Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks (September 2002).

J. C. Wagner and C. V. Parks, Parametric Study of the Effect of Burnable Poison Rods for PWR Burnup Credit, NUREG/CR-6761 (ORNL/TM-2000/373), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2002.

J. C. Wagner and C. E. Sanders, "Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit," Nucl. Technol. 139, 1-36 (August 2002).

2001

J. Anno, G. Poullot, E. Girault, P. Fouillaud, D. Hynek, and H. Toubon, "Status of the joint French ISPN/COGEMA Qualification Programme of Fission Products," 35382.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV, November 11-15, 2001.

M. C. Brady Raap, et al., Overview of the Burnup Credit Activities of the Organisation for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA), RAMTRANS 12(4), 213 (2001).

K. W. Cummings and S. E. Turner, "Design of Wet Storage Racks for Spent BWR Fuel," 35608.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

M. D. DeHart, "A Stochastic Method for Estimating the Effect of Isotopic Uncertainties in Spent Nuclear Fuel," ORNL/TM-2001/83, UT-Battelle, LLC, Oak Ridge National Laboratory, September 2001.

M. D. DeHart, " SAS2D — A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel," 35583.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

M. Doucet et al., "Framatome ANP Capabilities in Nuclear Criticality Safety Studies for Transport Packages and Storage Installations," in Proc.of The 13^th International Symposium on the Packaging and Transportation of Radioactive Material (PATRAM2001), September 3-7, 2001, Chicago, IL.

P. Dyck, "Overview of the Burnup Credit Activities at the IAEA," in Proc. of The 13^th International Symposium on the Packaging and Transportation of Radioactive Material (PATRAM2001), September 3-7, 2001, Chicago, IL.

I. C. Gauld, Limited Burnup Credit in Criticality Safety Analysis: A Comparison of ISG-8 and Current International Practice, NUREG/CR-6702 (ORNL/TM-2001/83), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2001.

I. C. Gauld and J. C. Ryman, Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms Related to Transport and Interim Storage of High-Burnup LWR Fuel, NUREG/CR-6700 (ORNL/TM-2000/284), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2001.

I. C. Gauld and S. M. Bowman, STARBUCS: A Prototypic SCALE Control Module for Automated Criticality Safety Analyses Using Burnup Credit, NUREG/CR-6748 (ORNL/TM-2001/33), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2001.

I. C. Gauld and C. E. Sanders, "Development and Applications of a Prototypic SCALE Control Module for Automated Burnup Credit Analysis," 35238.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

S. K. Kessler, K. N. Schwinkendorf, D. G. Erickson, and H. Toffer, "Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project," 35752.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

D. Lancaster and C. T. Rombough, "Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin," 35612.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

C. Lavarenne et al., "A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products," in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

A. LeBrun and G. Bignan, "Nondestructive Assay of Nuclear Low-Enriched Uranium Spent Fuels for Burnup Credit Application," Nucl. Technol. 135, 216 (2001).

A. LeBrun et al., "Average Burnup and Axial Burnup Profile Measurement for Burnup Credit Application," in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

I. Mitsuhashi et al., "Accuracy Evaluation of Reactor Records Based on Solution Analyses Data of Spent Fuels at JNC Tokai Reprocessing Plant," in Proc. of The 13^th International Symposium on the Packaging and Transportation of Radioactive Material (PATRAM2001), September 3-7, 2001, Chicago, IL.

J-C. Neuber, "Effects of the Presence of Axial Blankets and Integral Burnable Absorbers on the End Effect of PWR Burnup Profiles," in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

Y. Nomura et al., "Development of Burnup Credit Evaluation Methods at JAERI," in Proc. of The 13^th International Symposium on the Packaging and Transportation of Radioactive Material (PATRAM2001), September 3-7, 2001, Chicago, IL.

P. O'Leary. 2001. "Final Draft of BUV White Paper." E-mail from P. O'Leary to D. Salmon and D. Thomas, January 18, 2001, with attachment. ACC: MOL.20010313.0307; LSN#DN2002039840 and DN2001228782.

P. M. O'Leary and J. M. Scaglione, "An Empirical Approach to Bounding the Axial Reactivity Effects of PWR Spent Nuclear Fuel," Trans. Am. Nucl. Soc. 84, 352-353 (2001).

J. M. Paratte and P. Grimm, "Limited Burnup Credit for Increased Fuel Enrichments in a Swiss PWR Storage Pool," 35569.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

C. V. Parks, I. C. Gauld, J. C. Wagner, B. L. Broadhead, M. D. DeHart, and D. D. Ebert, "Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks," pp. 139-161 in Proc. of U.S. NRC 28^th Water Reactor Safety Information Meeting, October 23-25, 2000, Bethesda, MD (May 2001).

C. V. Parks and R. Y. Lee, "Research Supporting Implementation of Burnup Credit in Transport and Storage Casks," 27_4.pdf in Proc. of ANS 2001 International High-Level Radioactive Waste Management Conference, April 29-May 3, 2001, Las Vegas, NV (May 2001).

C. V. Parks, B. L. Broadhead, M. D. DeHart, and I. C. Gauld, "Validation Issues for Depletion and Criticality Analysis in Burnup Credit," pp. 167-179 in Proc. of International Atomic Energy Agency (IAEA) Technical Committee Meeting on the Evaluation and Review of the Implementation of Burnup Credit in Spent Fuel Management Systems, July 10-14, 2000, Vienna, Austria (August 2001).

C. V. Parks, M. D. DeHart, and J. C. Wagner, "Phenomena and Parameters Important to Burnup Credit," pp. 233-247 in Proc. of International Atomic Energy Agency (IAEA) Technical Committee Meeting on the Evaluation and Review of the Implementation of Burnup Credit in Spent Fuel Management Systems, July 10-14, 2000, Vienna, Austria (August 2001).

C. V. Parks and J. C. Wagner, "Issues for Effective Implementation of Burnup Credit," pp. 298-308 in Proc. of International Atomic Energy Agency (IAEA) Technical Committee Meeting on the Evaluation and Review of the Implementation of Burnup Credit in Spent Fuel Management Systems, July 10-14, 2000, Vienna, Austria (August 2001).

C. V. Parks, J. C. Wagner, I. C. Gauld, B. L. Broadhead, and C. E. Sanders, "U.S. Regulatory Research Program for Implementation of Burnup Credit in Transport Casks," in Proc. of The 13^th International Symposium on the Packaging and Transportation of Radioactive Material (PATRAM2001), September 3-7, 2001, Chicago, IL.

C. W. Reamer and A. V. Gil. 2001. Summary Highlights of NRC/DOE Technical Exchange and Management Meeting on Pre-Closure Safety. Meeting held July 24-26, 2001, Las Vegas, Nevada. Washington, D.C.: U.S. Nuclear Regulatory Commission. ACC: MOL20011003.0091.

C. E. Sanders and M. D. DeHart, "Comparison of Computational Estimations of Reactivity Margin From Fission Products and Minor Actinides in PWR Burnup Credit," 35765.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

C. E. Sanders and J. C. Wagner, "Impact of Integral Burnable Absorbers on PWR Burnup Credit Criticality Safety Analyses," 35235.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

C. E. Sanders and J. C. Wagner, "Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses," 35281.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

J. M. Scaglione, "Spent Fuel Criticality Benchmark Experiments," 35599.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

K. van der Meer et al., "The Burn-Up Credit Experimental Programme REBUS," 35326.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

J. C. Wagner, Computational Benchmark for Estimation of the Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit, NUREG/CR-6747 (ORNL/TM-2000/306), prepared for the U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2001.

J. C. Wagner and C. V. Parks, "A Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent-Fuel Pool Storage," Nucl. Technol. 136, 130-140 (October 2001).

J. C. Wagner, "Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety," 35218.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11-15, 2001, Reno, NV.

2000

W. J. Anderson, "Temperature Effects on Reactivity of Commercial Reactor Criticals," Trans. Am. Nucl. Soc. 83, 141-142 (2000).

W. J. Anderson P. M. O'Leary, and J. M. Scaglione, "Selection of Reactor Criticals as Benchmarks for Spent Nuclear Fuels," Trans. Am. Nucl. Soc. 83, 140-141 (2000).

M. C. Brady Raap, Y. Nomura, and E. Sartori, "Overview of the Burnup Credit Activities at OECD/NEA/NSC," Trans. Am. Nucl. Soc. 83, 117-119 (2000).

B. L. Broadhead, "Value Rankings of Selected Critical Experiments for Burnup Credit Validations," Trans. Am. Nucl. Soc. 83, 124-126 (2000).

D. E. Carlson and C. J. Withee, "Regulatory Status of Burnup Credit for Spent-Fuel Storage and Transport Casks," Trans. Am. Nucl. Soc. 83, 115 (2000).

D. E. Carlson, C. J. Withee, and C. V. Parks, "Spent Fuel Burnup Credit in Casks: An NRC Perspective," pp. 419-436 in Proc. of the Twenty-Seventh Water Reactor Safety Information Meeting, October 25-27, 1999, Bethesda, MD, NUREG/CP-0169, U.S. Nuclear Regulatory Commission, March 2000.

C. Connell and R. Kochendarfer, "The Effect of Half-Life and Branching Fraction Uncertainties on the Effective Neutron Multiplication Factor," Trans. Am. Nucl. Soc. 83, 124 (2000).

M. D. DeHart, "A Statistical Method for Estimating the Net Uncertainty in the Prediction of k Based on Isotopic Uncertainties," Trans. Am. Nucl. Soc. 83, 121-122 (2000).

T. W. Doering, "Dry Cask Storage and Transportation Burnup Credit," Trans. Am. Nucl. Soc. 83, 115-116 (2000).

D. D. Ebert and R. Y. Lee, "NRC Burnup Credit Research Program," Trans. Am. Nucl. Soc. 83, 117 (2000).

I. C. Gauld, SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configurations, ORNL/TM-1999/247, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, March 2000.

G. A. Harms, "The Nuclear Energy Research Initiative Burnup Credit Critical Experiment," Trans. Am. Nucl. Soc. 83, 119-120 (2000).

D. P. Henderson, "PWR Radiochemical Assay Benchmarks Using SAS2H and CASMO," Trans. Am. Nucl. Soc. 83, 135-136 (2000).

Implementation of Burnup Credit In Spent Fuel Management Systems, Proceedings of a Technical Committee Meeting, IAEA, 10-14 July 2000, Vienna.

R. A. Kochendarfer and D. P. Henderson, "Reconciliation of Isotopic Uncertainty Between Assays and Integral Benchmarks," Trans. Am. Nucl. Soc. 83, 122-124 (2000).

W. H. Lake and H. P. Dyck, "IAEA TCM 2000: An International Meeting on Burnup Credit Applications," Trans. Am. Nucl. Soc. 83, 116-117 (2000).

D. B. Lancaster et al., "Actinide-Only Burnup Credit License Application: the CASTOR X/32 S Cask Modeling Details," Trans. Am. Nucl. Soc. 83, 126-127 (2000).

NUREG-1617, Standard Review Plan for Transportation Packages for Spent Nuclear Fuel — Final Report, USNRC, Washington, D.C., March 2000.

H. Okuno et al., "OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIA: Criticality Calculations of BWR Spent Fuel Assemblies in Storage and Transport," NEA/NSC/DOC(2000)12, JAERI, September 2000.

P. M. O'Leary and M. L. Pitts, "Effects of Integral Burnable Absorbers on PWR Spent Nuclear Fuel," Trans. Am. Nucl. Soc. 83, 128-130 (2000).

C. V. Parks, M. D. DeHart, and J. C. Wagner, Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel, NUREG/CR-6665 (ORNL/TM-1999/303), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2000.

M. L. Pitts and P. M. O'Leary, "Modeling BWR Spent-Fuel Isotopics with SAS2H and CASMO-3," Trans. Am. Nucl. Soc. 83, 136-137 (2000).

C. W. Reamer. 2000. "Safety Evaluation Report for Disposal Criticality Analysis Methdology Topical Report, Revision 0." Letter from C. W. Reamer (NRC) to S. J. Brocoum (DOE/UMSCO), June 26, 2000, with enclosure. ACC: MOL.20000919.0157.

J. J. Sapyta et al., "Use of Reactor-Follow Data to Determine Biases and Uncertainties for PWR Spent Nuclear Fuel," Trans. Am. Nucl. Soc. 83, 137-138 (2000).

J. M. Scaglione et al., "Applicability of CRC Benchmark Experiments for Burnup Credit Validation," Trans. Am. Nucl. Soc. 83, 138-140 (2000).

J. C. Wagner and M. D. DeHart, Review of Axial Burnup Distribution Considerations for Burnup Credit Calculations, ORNL/TM-1999/246, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, March 2000.

J. C. Wagner and C. V. Parks, A Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage, NUREG/CR-6683 (ORNL/TM-2000/230), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2000.

J. C. Wagner, M. D. DeHart, and B. L. Broadhead, Investigation of Burnup Credit Modeling Issues Associated with BWR Fuel, ORNL/TM-1999/193, UT-Battelle, LLC, Oak Ridge National Laboratory, October 2000.

J. C. Wagner and C. V. Parks, "Impact of Burnable Poison Rods on PWR Burnup Credit Criticality Safety Analyses," Trans. Am. Nucl. Soc. 83, 130-134 (2000).

1999

F. Barbry, A. Laviron, P. Fouillaud, P. Cousinou, and G. Poullot, "Experimental Criticality Study Programmes and Test Potential of the IPSN/VALDUC Criticality Laboratory," A411.pdf in Proc. of the Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France.

J. Basselier, T. Maldague, A. Renard, H. Abderrahim, S. Bodart, P. D'hondt, K. Van der Meer, V. Rypar, C. Svoboda, and I. Vasa, "Critical Experiment with Spent Fuel for Burn-Up Credit Validation (REBUS International Programme)," C215.pdf in Proc. of the Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999,Versailles, France.

M. D. DeHart, Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term Disposal Criticality Safety, ORNL/TM-1999/99, Lockheed Martin Enrergy Research Corp., Oak Ridge National Laboratory, August 1999.

H. P. Dyck, J. C. Neuber, W. H. Lake, and A. Santamarina, "Overview of the Burnup Credit Activities at the IAEA," C212.pdf in Proc. of the Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France.

E. Fuentes, D. B. Lancaster, and M. Rahimi, "Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel — II: Validation," Nucl. Technol. 125, 271 (1999).

N. Harris et al., "The Development of a Burn-up Criticality Safety Case for the Thorp Reprocessing Plant," D212.pdf in Proc. of the Sixth International Conference on Nuclear Criticality, September 20-24, 1999, Versailles, France.

O. W. Hermann, San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses, ORNL/TM-1999/108, Lockheed Martin Energy Research, Oak Ridge National Laboratory, September 1999.

C. H. Kang and D. B. Lancaster, "Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel — III: Bounding Treatment of Spatial Burnup Distributions," Nucl. Technol. 125, 292 (1999).

C. Lavarenne, E. Letang, O. Dekens, M. Doucet, J. P. Grouiller, N. Thiollay, and E. Guillou, "Taking Burnup Credit into Account in Criticality Studies: The Situation as it is Now and the Prospect for the Future," D213.pdf in Proc. of the Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France.

D. B. Lancaster, E. Fuentes, C. H. Kang, and M. Rahimi, "Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel — I: Methodology Overview," Nucl. Technol. 125, 255 (1999).

M. Maillot, E. Guillou, D. Biron, and S. Janski, "Search for an Envelope Axial Burnup Profile for Use in PWR Criticality Studies with Burnup Credit," B423.pdf in Proc of Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France.

J. C. Neuber, "Criticality Analysis of BWR Spent Fuel Storage Facilities Inside Nuclear Power Plants," A421.pdf in Proc. of the Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France.

H. Okuno, Y. Naito, K. Suyama, and Y. Ando, "International Studies on Burnup Credit Criticality Safety by an OECD/NEA Working Group: Calculation Benchmarks for BWR Spent Fuels," C211.pdf in Proc. of the Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France.

J. M. Paratte, "Reactivity Calculations for a High Density Spent Fuel Storage Pool for BWR Assemblies," P1_07.pdf in Proc. of the Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France.

Spent Fuel Project Office Interim Guidance — 8, Rev. 1 - Limited Burnup Credit, U.S. Nuclear Regulatory Commission, July 30, 1999.

N. Thiollay et al., "Burnup Credit for Fission Product Nuclides in PWR (UO₂) Spent Fuels," D211.pdf in Proc. of the Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France.

P. R. Thorne, G. J. O'Conner, and R. L. Bowden, "The Current Status of the Methods Adopted by BNFL in Claiming Credit for Burnup in Criticality Safety Assessments," D215.pdf in Proc. of Sixth International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France.

T. E. Valentine, Review of Subcritical Source-Driven Noise Analysis Measurements, ORNL/TM-1999/288, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, November 1999.

1998

M. J. Anderson and D. P. Henderson, "BWR Benchmarking for Yucca Mountain Disposal Criticality Methodology," Trans. Am. Nucl. Soc. 79, 281 (1998).

B. L. Broadhead, K-infinite Trends with Burnup, Enrichment, and Cooling Time for BWR Fuel Assemblies, ORNL/M-6155, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, August 1998.

R. J. Cacciapouti, G. M. Lam, P. A. Theriault, and P. M. Delmolino, "Determination of the Uncertainty in Assembly Average Burnup," Trans. Am. Nucl. Soc. 79, 277 (1998).

CRWMS M&O 1998 Summary Report of Commercial Reactor Criticality Data for Sequoyah Unit 2, B00000000-01717-5705-00064 REV 01, Las Vegas, NV: CRWMS M&O. MOL.19980716.0015.

CRWMS M&O 1998 Summary Report of Commercial Reactor Criticality Data for Crystal River Unit 3, B00000000-01717-5705-00060 REV 01, Las Vegas, NV: CRWMS M&O. MOL.19980728.0189.

Determination of the Accuracy of Utility Spent Fuel Burnup Records — Interim Report, Electric Power Research Institute, TR-109929, May 1998.

Disposal Criticality Analysis Methodology Topical Report, YMP/TR-004Q, Revision 0, U.S. Department of Energy, Office of Civilian Radioactive Waste Management, Yucca Mountain Site Characterization Project, November 1998.

P. J. Finck and C. G. Stenberg, "Fission Product Margin in Burnup Credit Analyses," Trans. Am. Nucl. Soc. 79, 279 (1998).

S. E. Fisher and F. C. Defilippo, Neutronics Benchmark for the Quad Cities-1 (Cycle 2) Mixed-Oxide Assembly Irradiation, ORNL/TM-13567, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, April 1998.

"Guidance on the Regulatory Requirements for Criticality Safety Analysis of Fuel Storage at Light-Water Reactor Power Plants," NRC memorandum from L. I. Kopp to T. Collins, August 19, 1998, U.S. Nuclear Regulatory Commission.

O. W. Hermann, M. D. DeHart, and B. D. Murphy, Evaluation of Measured LWR Spent Fuel Composition Data for Use in Code Validation, ORNL/M-6121, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, February 1998.

O. W. Hermann, P. R. Daniel, and J. C. Ryman, ORIGEN-S Decay Data Library and Half-Life Uncertainties, ORNL/TM-13624, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, September 1998.

O. W. Hermann and M. D. DeHart, Validation of SCALE (SAS2H) Isotopic Predictions for BWR Spent Fuel, ORNL/TM-13315, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, September 1998.

C. H. Kang and D. B. Lancaster, Conservative Axial Burnup Distributions for Actinide-Only Burnup Credit, DOE/RW-00134, U.S. Department of Energy, 1998.

R. Kimpland, P. Jaegers, and C. Cappiello, "SHEBA/²³³U Worth Experiments," Trans. Am. Nucl. Soc. 79, 280 (1998).

D. Lancaster, C. Kang, and W. Lake, "Value of ²³⁶U to Actinide-Only Burnup Credit," Trans. Am. Nucl. Soc. 79, 276 (1998).

G. I. Maldonado and E. Fuentes, "Determination of Limiting Cask Configuration by Simulated Annealing," Trans. Am. Nucl. Soc. 79, 278 (1998).

B. D. Murphy, Prediction of the Isotopic Composition of UO₂ Fuel from a BWR Analysis of the DU1 Sample from the Dodewaard Reactor, ORNL/TM-13687, Lockheed Martin Energy Research Corporation, Oak Ridge National Laboratory, October 1998.

J. C. Neuber, "Burnup Credit Applications to PWR and BWR Fuel Assembly Wet Storage Systems," Vol. 1, pp. 631-638 in Proc. of International Conference Physics of Nuclear Science and Technology, October 5-8, 1998, Long Island, NY.

A. Nouri, OECD/NEA Burnup Credit Criticality Benchmark — Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask, IPSN/98-05 (NEA/NSC/DOC(98)1), Institut de Protection et de Surete Nucleaire, May 1998.

C. E. Olson, D. R. Bronowski, W. McMurtry, R. Ewing, R. Jordon, and D. Rivard, "The Fork+ Burnup Measurement System: Design and First Measurement Campaign," Trans. Am. Nucl. Soc. 79, 282 (1998).

Topical Report on Actinide-Only Burnup Credit for PWR Spent NuclearFuel Packages, DOE/RW-0472, Rev. 2, U.S. Department of Energy, September 1998.

K. D. Wright, "Commercial Reactor (PWR) Critical Evaluations for Benchmarking SAS2H and MCNP4A," in Proc. of the Eight International High Level Waste Management Conference, May 11-14, 1998, Las Vegas, NV.

1997

R. J. Cacciapouti and S. Van Volkinburg, "Axial Burnup Profile Database for Pressurized Water Reactors," YAEC-1937, Yankee Atomic Electric Company (May 1997). Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as DLC-201.

C. H. Kang and D. B. Lancaster, Depletion and Package Modeling Assumptions for Actinide-Only Burnup Credit, DOE/RW-0495, U.S. Department of Energy, May 1997.

C. H. Kang and D. B. Lancaster, E nd Effect K_eff Bias Curve for Actinide-Only Burnup Credit Casks, DOE/RW-00134, U.S. Department of Energy, 1997.

C. Kang, M. Nichol, D. Lancaster, K. Waldrop, and J. Thornton, Horizontal Burnup Gradient Datafile for PWR Assemblies, DOE/RW-0496, U.S. Department of Energy, May 1997.

Office of Civilian Radioactive Waste Management, Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages, DOE/RW-0472 Rev. 1, U.S. Department of Energy, Office of Civilian Radioactive Waste Management, May 1997.

Office of Civilian Radioactive Waste Management M&O Contractor, Summary Report of Commercial Reactor Critical Analyses Performed for the Disposal Criticality Analysis Methodology, B00000000-01717-5705-00075 REV 00, U.S. Department of Energy, Yucca Mountain Site Characterization Project Office, September 1997.

T. A. Parish and C. H. Chen, Bounding Axial ProfileAnalysis for the Topical Report Database, Nuclear Engineering Dept, Texas A&M University, March 1997.

M. Rahimi, E. Fuentes, and D. Lancaster, Isotopic and Criticality Validation for PWR Actinide-Only Burnup Credit, DOE/RW-0497, U.S. Department of Energy, May 1997.

1996

S. M. Bowman and T. Suto, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 5 — North Anna Unit 1 Cycle 5, ORNL/TM-12294/V5, Lockheed Martin Marietta Energy Research Corp., Oak Ridge National Laboratory, October 1996.

M. D. DeHart, Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages, ORNL/TM-12973, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, May 1996.

M. D. DeHart, M. C. Brady, and C. V. Parks, OECD/NEA Burnup Credit Calculational Criticality Benchmark Phase I-B Results, ORNL-6901 (NEA/NSC/DOC(96)-06), Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, June 1996.

M. D. DeHart and O. W. Hermann, An Extension of the Validation of SCALE (SAS2H) Isotopic Predictions for PWR Spent Fuel, ORNL/TM-13317, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, September 1996.

Regulations for the Safe Transport of Radioactive Material, 1996 Edition. IAEA Safety Standards Series No. ST-1, International Atomic Energy Agency (1996).

"Spent Nuclear Fuel Discharges from U.S. Reactors — 1994," SR/CNEAF/96-01, Energy Information Administration, U.S. Department of Energy, February 1996.

M. Takano and H. Okuno, OECD/NEA Burnup Credit Criticality Benchmark — Result of Phase IIA, NEA/NSC/DOC(96)01, JAERI, February 1996.

M. Takano and H. Okuno, OECD/NEA Burnup Credit Criticality Benchmark — Result of Phase IIA, JAERI-Research-96-003 (NEA/NSC/DOC(61)01), Japan Atomic Energy Research Institute, February 1996.

1995

J. Anno, P. Fouilland, P. Grivot, and G. Poullot, "Description and Exploitation of Benchmarks Involving ¹⁴⁹Sm, A Fission Product Tacking Part in the Burnup Credit in Spent Fuels," Vol. I, pp. 5 C 17 in Proc. of the Fifth International Conference on Nuclear Criticality Safety, September 17-21, 1995, Albuquerque, NM.

R. L. Bowden, P. R. Thorne, and P. I. D. Strafford, "The Methodology Adopted by British Nuclear Fuels PLC in Claiming Credit for Reactor Fuel Burnup in Criticality Safety Assessments," Vol. I, pp. 1B C 3 - 1B C 10 in Proc. of the Fifth International Conference on Nuclear Criticality Safety, September 17-21, 1995, Albuquerque, NM.

J. K. Boshoven, "Burnup Credit Experiences with the GA-4 Cask," Nucl. Technol. 110, 33-39 (1995).

S. M. Bowman and O. W. Hermann, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3 — Surry Unit 1 Cycle 2, ORNL/TM-12294/V3, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, March 1995.

S. M. Bowman, O. W. Hermann, and M. C. Brady, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 2 — Sequoyah Unit 2 Cycle 3, ORNL/TM-12294/V2, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, March 1995.

S. M. Bowman, M. D. DeHart, and C. V. Parks, "Validation of SCALE-4 for Burnup Credit Applications," Nucl. Technol. 110, 53 (April 1995).

B. L. Broadhead, M. D. DeHart, J. C. Ryman, J. S. Tang, and C. V. Parks, Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage for LWR Spent Fuel, ORNL/TM-12742, Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, June 1995.

B. L. Broadhead, "Feasibility Assessment of Burnup Credit in the Criticality Safety Analysis of Shipping Casks with Boiling Water Reactor Spent Fuel," Nucl. Technol. 110, 1-21 (1995).

R. J. Cacciapouti and S. Van Volkinburg, Axial Profile Database for the Combustion Engineering 14 '14 Fuel Design, YAEC-1918, Yankee Atomic Electric Company, April 1995.

J. M. Conde and M. Recio, "Evaluation of Burnup Credit for Fuel Storage Analysis — Experience in Spain," Nucl. Technol. 110, 22-32 (1995).

M. D. DeHart, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 1 — Summary, ORNL/TM-12294/V1, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, March 1995.

M. D. DeHart, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 4 — Three Mile Island Unit 1 Cycle 5, ORNL/TM-12294/V4, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, March 1995.

M. D. DeHart and S. M. Bowman, Analysis of Fresh Fuel Criticality Experiments Appropriate for Burnup Credit Validation, ORNL/TM-12959, Lockheed Martin Energy Research Systems Inc., Oak Ridge National Laboratory, October 1995.

G. A. Harms, F. J. Davis, and J. T. Ford, "The Spent Fuel Safety Experiment," Vol. I, pp. 5 C 3 - 5 C 9 in Proc. of The Fifth International Conference on Nuclear Criticality, September 17-21, 1995, Albuquerque, NM.

O. W. Hermann, S. M. Bowman, M. C. Brady, and C. V. Parks, Validation of the SCALE System for PWR Spent Fuel Isotopic Composition Analyses, ORNL/TM-12667, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, March 1995.

Y. Naito, M. Takano, M. Kurosawa, and T. Suzaki, "Study of the Criticality Safety Evaluation Method for Burnup Credit in JAERI," Nucl. Technol. 110 (1995).

1994

P. L. Holman and W. A. Wittkopf, "Axial Burnup Profiles and Spent Fuel Rack Burnup Credit," Vol. III, pp. 378-383 in Proc. of the 1994 Topical Meeting on Advances in Reactor Physics, April 11-15, 1994, Knoxville, TN.

Y. Naito, M. Kurosawa, and T. Kaneko, Data Book of the Isotopic Composition of Spent Fuel in Light Water Reactors, JAERI-M 94-034, Japan Atomic Energy Research Institute, 1994.

T. Suto, S. M. Bowman, and C. V. Parks, "The Reactivity of Nuclide Buildup and Decay During Long-Term Fuel Storage," Vol. 2, p. 831 in Proc. of the Fifth Annual International Conference on High Level Radioactive Waste Management, May 22-26, 1994, Las Vegas, NV.

M. Takano, OECD/NEA Burnup Credit Criticality Benchmark — Result of Phase-1A, JAERI-M 94-003 (NEA/NSC/DOC(93)22, Japan Atomic Energy Research Institute, 1994.

1993

S. M. Bowman, O. W. Hermann, and M. C. Brady, "Burnup Credit Validation of SCALE‑4 Using Light Water Reactor Criticals," Trans. Am. Nucl. Soc. 68(A), 241 (1993).

S. M. Bowman and H. Taniuchi, "Burnup Credit Validation of SCALE-4 Using Mixed-Oxide Critical Experiments," Trans. Am. Nucl. Soc. 68(A), 241 (1993).

1992

M. C. Brady, T. L. Sanders, K. D. Seager, and W. H. Lake, "Burnup Credit Issues in Transportation and Storage," Vol. 1, pp. 39-46 in Proc. 10th International Symposium on Packaging and Transportation of Radioactive Materials, September 13-18, 1992, Yokohama City, Japan.

Characteristics of Potential Repository Wastes, DOE/RW-0184-R1, July 1992.

C. R. Marotta, "Reactivity End-Effects Estimates Using a K Perturbation Model," Vol. 2, p. 2165 in Proc. of the International High Level Radioactive Waste Management Conference, April 12-16, 1992, Las Vegas, NV, American Nuclear Society (1992).

Proceedings: 1991 EEI/UWASTE-EPRI Workshop on At-Reactor Spent Fuel Storage, EPRI-TM-100676, May 1992.

1991

M. C. Brady and T. L. Sanders, "A Validated Methodology for Evaluating Burnup Credit in Spent Fuel Casks," Vol. 1, pp. II-68 - II-82 in Proc. of the International Conference on Nuclear Criticality Safety, September 9-13, 1991, Christ Church, Oxford, United Kingdom.

J. M. Conde, M. Recio, and F. J. Ramon, "Criticality Safety Evaluation of Fuel Storage Pools in Spain," Vol. 1, pp. II-126 - II-132 in Proc. of the International Conference on Nuclear Criticality Safety, September 9-13, 1991, Christ Church, Oxford, United Kingdom.

R. J. Guenther et al., Characterization of Spent Fuel Approved Testing Material - ATM-104, PNL-5109-104, Pacific Northwest Laboratory, 1991.

K. Itahara and S. Shimada, "Effect of Burnup Distributions on Criticality Safety Designs Taking Credit for Fuel Burnup," in Proc. of 3^rd International Conference on Nuclear Fuel Reprocessing Waste Management, April 14-18, 1991, Sendai, Japan.

1990

S. R. Bierman, "Benchmark Data for Validating Irradiated Fuel Compositions Used in Criticality Calculations," Trans. Am. Nucl. Soc. 62, 311-312 (1990).

J. K. Boshoven and S-D. Su, "Burnup Credit Application for GA-4 Transportation Casks," Trans. Am. Nucl. Soc. 62, 318-319 (1990).

M. C. Brady, C. V. Parks, and C. R. Marotta, "End Effects in the Criticality Analysis of Burnup Credit Casks," Trans. Am. Nucl. Soc. 62, 317-318 (1990).

B. L. Broadhead, "Burnup Credit Feasibility for BWR Spent-Fuel Shipments," Trans. Am. Nucl. Soc. 62, 319-321 (1990).

R. W. Carlson and L. E. Fisher, "Impact of Uncertainties in the Effects of Burnup on Criticality Safety Licensing Criteria," Trans.Am. Nucl. Soc. 62, 314 (1990).

C. R. Marotta, "Alternative Certification Options for a Burnup-Credit Spent-Fuel Cask," Trans. Am. Nucl. Soc. 62, 313-314 (1990).

D. Napolitano and D. Adli, "Burnup Credit Analysis of a 31-Assembly Cask," Trans. Am. Nucl. Soc. 62, 315-317 (1990).

D. Napolitano and D. Adli, "Validation of the YAEC Burnup Credit Methodology," Trans. Am. Nucl. Soc. 62, 305-306 (1990).

J-P. Renier and C. V. Parks, "Reactor Critical Calcuations for Validation of Burnup Credit Analysis Methods," Trans. Am. Nucl. Soc. 62, 308-310 (1990).

T. L. Sanders and R. M. Westfall, "Feasibility and Incentives for Burnup Credit in Spent Fuel Transport Casks," Nucl. Sci. Eng. 104, 66-77 (1990).

M. H. Watmough and A. M. Evans, "Burnup Credit: Calculational Schemes and Related Considerations," Trans. Am. Nucl. Soc. 62, 306-308 (1990).

1989

S. R. Bierman, "Feasibility of Performing Criticality Experiments with Spent LWR Fuel," pp. 179-188 in Proc. of a Workshop on the Use of Burnup Credit in Spent Fuel Transport Casks, February 21-22, 1988, Washington D.C., SAND89-0018, TTC-0884, UC-820, Sandia National Laboratory, October 1989.

D. G. Napolitano, "Uncertainties in Criticality Analysis Which Affect the Storage and Transportation of LWR Fuel," pp. 297-303 in Proc. of the International Topical Meeting on Safety Margins in Criticality Safety, November 26-30, 1989, San Francisco, CA.

C. V. Parks, "An Approach for Verifying Analysis Techniques Applicable to the Burnup Credit Technical Issue," pp. 189-196 in Proc. of a Workshop on the Use of Burnup Credit in Spent Fuel Transport Casks, February 21-22, 1988, Washington D.C., SAND89-0018, TTC-0884, UC-820, Sandia National Laboratory (October 1989).

C. V. Parks, "Parametric Neutronic Analyses Related to Burnup Credit Cask Design," pp. 21-43 in Proc. of a Workshop on the Use of Burnup Credit in Spent Fuel Transport Casks, Washington D.C., February 21-22, 1988, SAND89-0018, TTC-0884, UC-820, Sandia National Laboratory, October 1989.

T. L. Sanders, editor, "Proceedings of a Workshop on the Use of Burnup Credit in Spent Fuel Transport Casks," February 21-22, 1988, Washington D.C., SAND89-0018, TTC-0884, UC-820, Sandia National Laboratory, October 1989.

S. E. Turner, "An Uncertainty Analysis — Axial Burnup Distribution Effects," pp. 167-177 in Proc. Workshop Use of Burnup Credit in Spent Fuel Transport Casks, February 23-24, 1988, Washington D.C., SAND89-0018, TTC-0884, UC-820, T. L. Sanders, Ed., Sandia National Laboratory, October 1989.

B. H. Wakeman and S. A. Ahmed, "Evaluation of Burnup Credit for Dry Storage Casks," EPRI NP-6494, Electric Power Research Institute (August 1989).

1988

R. J. Guenther et al., Characterization of Spent Fuel Approved Testing Material - ATM-103, PNL-5109-103, Pacific Northwest Laboratory, 1988.

R. J. Guenther et al., Characterization of Spent Fuel Approved Testing Material - ATM-106, PNL-5109-106, Pacific Northwest Laboratory, 1988.

1987

W. A. Boyd, "Determining Burnup Credit Requirements in Spent-Fuel Storage Racks Using Reactivity Equivalencing," Trans. Am. Nucl. Soc. 55, 393-394 (1987).

W. A. Boyd and G. N. Wrights, "Past Experience and Future Needs for the Use of Burnup Credit in LWR Fuel Storage," Trans. Am. Nucl. Soc. 55, 396 (1987).

Characteristics of Spent Fuel, High-Level Waste, and Other Radioactive Wastes Which May Require Long-Term Isolation

D. R. Harris, "Criticality of Spent Reactor Fuel," Trans. Am. Nucl. Soc. 55, 396-397 (1987)

L. Maubert, "The Burn-Up Consideration in the Criticality Safety of Irradiated LWR Fuel Cycle Plants," pp. 379-382 in Proc. of the International Seminar on Nuclear Criticality Safety, October 19-23, 1987, Tokyo, Japan.

D. G. Napolitano, "Analysis of Burnup Credit in Fuel Storage with CASMO," Trans. Am. Nucl. Soc. 55, 398-399 (1987).

J. P. Roberts, "Burnup Credit Considerations in Dry Spent-Fuel Storage Licensing," Trans. Am. Nucl. Soc. 55, 391 (1987).

T. L. Sanders et al., "Burnup Credit in the Design of Spent-Fuel Shipping Casks," Trans. Am. Nucl. Soc. 55, 391-392 (1987).

T. L. Sanders, R. M. Westfall, and R. H. Jones, Feasibility and Incentives for the Consideration of Spent Fuel Operating Histories in the Criticality Analysis of Spent Fuel Shipping Casks, SAND87-0151, TTC-0713, UC-71, Sandia National Laboratory (August 1987).

S. E. Turner, "Storage of Burned PWR and BWR Fuel," Trans. Am. Nucl. Soc. 55, 394-395 (1987).

1986

D. G. Napolitano, D. P. Heinrichs, and J. P. Gorski, "CASMO-2 Spent-Fuel-Rack Criticality Analysis," Trans. Am. Nucl. Soc. 53, 300-301 (1986).

1985

J. O. Barner, Characterization of LWR Spent Fuel MCC-Approved Testing Material - ATM-101, PNL-5109, Rev. 1, Pacific Northwest Laboratory, 1985.

J. R. McCowan, "Generic Reactivity Equivalence of PWR Fuel in Spent Fuel Storage Racks," p. 135-141 in Proc. of a Topical Meeting on Criticality Safety in the Storage of Fissile Material, September 8-11, 1985, Jackson, WY.

1982

D. Doutriaux et al., "Validation of Criticality Calculation Methods for LWR Storage Pools," Trans. Am. Nucl. Soc. 41, 337-339 (1982).

D. G. Napolitano and R. J. Cacciapouti, "Criticality of High-Density, Boral-Poisoned, Fuel Racks for Maine Yankee," Trans. Am. Nucl. Soc. 41, 339-340 (1982).

1981

S. D. Atkin, Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the CLIMAX-Spent Fuel Test, HEDL-TME 80-89, Hanford Engineering Development Laboratory, 1981.

1979

P. Barbero et al., Post-Irradiation Analysis of the Gundremmingen BWR Spent Fuel, EUR-6301en, Joint Research Center Ispra and Karlsruhe Establishments, 1979.

1977

P. Barbero et al., Post-Irradiation Examination of the Fuel Discharged from the Trino Vercelles Reactor After the 2^nd Irradiation Cycle, EUR-5605e, Joint Nuclear Research Centre Ispra and Karlsruhe Establishments, 1977.

1972

A. M. Bresesti et al., Post-Irradiation Analysis of Trino Vercelles Reactor Fuel Elements, EUR-4909e, Joint Nuclear Research Centre Ispra and Karlsruhe Establishments, 1972.