Burnup Credit Related Publications

 

 

Last Updated:  February 1, 2011

 

 

 

 

 

 

 

 

 

 

NOTICE:

 

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 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 wagnerjc@ornl.gov.  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.

 

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.

V. N. Kucukboyaci and W. J. Marshall, "ISOCRIT: A Burnup Credit Tool for Spent Fuel Pool Storage Calculations," Proc. PHYSOR 2010, Pittsburgh, PA, May 9-14, 2010.

Burnup Credit Methodology, Spent Nuclear Fuel Transportation Applications, Report 1021050, Final Report, Electric Power Research Institute, Palo Alto, CA, July 2010.

D. E. Mueller, B. T. Rearden, and D. A. Reed, "Evaluation of Fission Product Critical Experiments and Associated Biases for Burnup Credit Validation," Proc. 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.

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

G. Radulescu, Propagation of Isotopic Bias and Uncertainty to Criticality Safety Analyses of PWR Waste Packages, ORNL/TM-2010/116, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2010.

G. Radulescu, I. C. Gauld, and G. Ilas, SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions, ORNL/TM-2010/44, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2010.

J. M. Scaglione and J. C. Wagner, "Burnup Credit Approach for the Proposed United States Repository at Yucca Mountain," Proc. 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.

J. C. Wagner, C. V. Parks, D. E. Mueller, and I. Gauld, "Review of Technical Studies in the United States in Support of Burnup Credit Regulatory Guidance," Proc. 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.

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.

I. C. Gauld and Y. Rugama, "Activities of the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel," presented at the IAEA International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Córdoba, Spain, October 27-30, 2009.

I. C. Gauld and Y. Rugama, "Experimental Isotopic Data Compiled by the OECD/NEA EGADSNF," Trans. Am. Nucl. Soc. 101, 773-775 (2009).

I. C. Gauld, G. Radulescu, and G. Ilas, "SCALE Validation Experience Using an Expanded Isotopic Assay Database for Spent Nuclear Fuel," presented at the IAEA International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Córdoba, Spain, October 27-30, 2009.

G. Ilas and I. C. Gauld, "SCALE 6 Analysis of Isotopic Assay Benchmarks for PWR Spent Fuel," Trans. Am. Nucl. Soc. 101, 691-693 (2009).

G. Radulescu and I. C. Gauld, "Enhancements to the Burnup Credit Criticality Safety Analysis Sequence in SCALE," IAEA International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition, Córdoba, Spain, October 27-30, 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.

G. Radulescu and I. C. Gauld, "STARBUCS: A SCALE Control Module for Automated Criticality Safety Analyses Using Burnup Credit," ORNL/TM-2005/39, Version 6, Vol. I, Sect. C10, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2009.

G. Radulescu and I. C. Gauld, "Enhancements to the Burnup Credit Criticality Safety Analysis Sequence in SCALE," Proc. 2009 Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance, Richland, WA, September 13-17, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009).

G. Radulescu, I. C. Gauld, and G. Ilas, "Evaluation of PWR Isotopic Composition Data," Trans. Am. Nucl. Soc. 101, 688-690 (2009).

Y. Rugama, R. Blomquist, M. Brady-Raap, B. Briggs, V. Rouyer, Y. Miyoshi, I. Gauld, and T. Ivanova, "Fuel Cycle Associated Activities of the OECD/NEA/NSC Working Party on Nuclear Criticality Safety," presented at GLOBAL 2009, 'The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives,' Paris, France, September 6–11, 2009.

Y. Rugama, I. Gauld, and K. Suyama, "OECD/NEA Expert Group on Assay Data Of Spent Nuclear Fuel," Proc. ICAPP 2009, Paper 9057, Tokyo, Japan, May 11–14, 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.

M. D. DeHart, I. C. Gauld, and K. Suyama, "Issues in Three-Dimensional Depletion Analysis of Measured Data Near the End of a Fuel Rod," Trans. Am. Nucl. Soc. 99, 663-666 (2008).

M. D. DeHart, I. C. Gauld, and K. Suyama, "Three-Dimensional Depletion Analysis of the Axial End of a Takahama Fuel Rod," International Conference on Reactor Physics, Nuclear Power: A Sustainable Resource, Interlaken, Switzerland, September 14–19, 2008.

G. Ilas and I. C. Gauld, "Analysis of Isotopic Assay Data from the MALIBU Program," presented at the International Conference on Reactor Physics, Nuclear Power: A Sustainable Resource, Interlaken, Switzerland, September 14–19, 2008.

D. E. Mueller, "Evaluation of the HTC Critical Experiment Data for Spent Nuclear Fuel," Trans. Am. Nucl. Soc. 98, 219-222 (2008).

D. E. Mueller and B. T. Rearden, "Using Cross-Section Uncertainty Data to Estimate Biases," Trans. Am. Nucl. Soc. 99, 389-390 (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-2007/83), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., September 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.

J. A. Roberts and D. E. Mueller, "Designing Critical Experiments in Support of Full Burnup Credit," Trans. Am. Nucl. Soc. 99, 391-393 (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.

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.

2007

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

C. T. Hsu and J. M. Scaglione. PWR Radial Burnup Gradient Reactivity Evaluation. ANL-DSC-NU-000001 REV 000. Las Vegas, Nevada: Sandia National Laboratories (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.

D. E. Mueller and J. C. Wagner, "Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation," Proc. IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, August 29-September 2, 2005, London, U.K., IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue: June 21, 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).

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.

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).

J. M. Scaglione. Commercial Spent Nuclear Fuel Igneous Scenario Criticality Evaluation. ANL-EBS-NU-000009 REV 00. Las Vegas, Nevada: Sandia National Laboratories (2007).

J. C. Wagner, Technical Work Plan for Development of Technical Data Needed to Justify Full Burnup Credit in Criticality Safety Licensing Analyses Involving Commercial Spent Nuclear Fuel, DOC.20070213.0002, TWP-EBS-MD-000019, Rev. 01, prepared for the U.S. Department of Energy Office of Civilian Radioactive Waste Management by Sandia National Laboratories, Las Vegas, NV, February 2007.

J. C. Wagner and D. E. Mueller, "Assessment of Benefits for Extending Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA," Proc. IAEA Technical Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, August 29-September 2, 2005, London, U.K., IAEA-TECDOC-1547, ISBN 92-0-103307-9, Date of Issue: June 21, 2007.

2006

I. C. Gauld and J. C. Wagner, "Status of Burnup Credit in the United States," presented at the Workshop on the Need for Post Irradiation Experiments to Validate Fuel Depletion Calculation Methodologies, OECD Nuclear Energy Agency, WPNCS, Prague, Czech Republic, December 2006.

I. C. Gauld, "Spent Fuel Isotopic Validation Activities in the United States: Status and Lessons Learned," Workshop on the Need for Post Irradiation Experiments to Validate Fuel Depletion Calculation Methodologies, OECD Nuclear Energy Agency, WPNCS, Prague, Czech Republic, December 2006.

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

A. H. Wells and J. M. Scaglione. Reactivity Effects of Isotopic Uncertainty for Burnup Credit Validation. 000-00C-WHS0-01500-000-00A. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2006).

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).

S. N. Williams and D. E. Mueller, "Survey of Operating Parameters for Use in Burnup Credit Calculations," Trans. Am. Nucl. Soc. 95, 269-273 (2006).

K. D. Wright and J. M. Scaglione. CRC Reactivity Calculations for Three Mile Island Unit 1. B00000000-01717-0210-00008 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (1998).

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 G. A. Harms, "Using the SCALE 5 TSUNAMI-3D Sequence in Critical Experiment Design," Trans. Am. Nucl. Soc. 93, 263-266 (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.

H. R. Radulescu and J. M. Scaglione. CSNF Assembly Type Sensitivity Evaluation for Pre- and Postclosure Criticality Analysis. CAL-DSU-NU-000013 REV 00A. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2005).

H. R. Radulescu and J. M. Scaglione. Criticality Calculation for 21-PWR Waste Package Configuration for Underburned Assemblies. CAL-DSU-NU-000015 REV 0A. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2005).

J. M. Scaglione. 21-PWR Site-Specific Canister Loading Curve Evaluation. 000-00C-HA00-00200-000-00A. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2005).

J. M. Scaglione. 21-PWR Waste Package Probability of Criticality Due to Misload. CAL-DSU-NU-000014 REV 00A. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (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. American Nuclear Society, 14th 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.

J. M. Scaglione. 21 PWR Waste Package With Absorber Plates Loading Curve Evaluation. CAL-DSU-NU-000006 REV 00C. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2004).

J. M. Scaglione. 44-BWR Waste Package Loading Curve Evaluation. CAL-DSU-NU-000008 REV 00A. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2004).

A. H. Wells, J. E. Huffer, and J. M. Scaglione. Isotopic Model for Commercial SNF Burnup Credit. CAL-DSU-NU-000007 REV 00B. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (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, EPRI, Palo Alto, CA: 2003.1003418.

K. R. Elam, J. C. Wagner, and C. V. Parks, Effects of Fuel Failure on Criticality Safety and Radiation Dose for Spent Fuel Casks, NUREG/CR-6835 (ORNL/TM-2002/255), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., September 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.

J. Huffer and J. M. Scaglione. Calculation of Isotopic Bias and Uncertainty for BWR SNF. CAL-DSU-NU-000003 REV 00A. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (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. 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.

C. E. Sanders and J. C. Wagner, Study of the Effect of Integral Burnable Absorbers on 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 2003.

J. M. Scaglione. Criticality Model Report. MDL-EBS-NU-000003 REV 01. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2003).

J. M. Scaglione. Preclosure Criticality Analysis Process Report. TDR-EBS-NU-000004 REV 01. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2003).

J. M. Scaglione. PWR Axial Burnup Profile Analysis. CAL-DSU-NU-000012 REV 00A. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (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), preapred 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. 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," 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, EPRI, 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. 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 M. D. DeHart, "Computational Benchmark of the 2-D Depletion Sequence SAS2D for Characterization of Spent Nuclear Fuel," in Proc. 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," 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," Trans. Am. Nucl. Soc. 86, 98–100 (June 2002).

J. M. Scaglione, "Isotopic Bias and Uncertainty for Burnup Credit Applications," Trans. Am. Nucl. Soc. 87, 105-107 (2002).

J. M. Scaglione. Calculation of Isotopic Bias and Uncertainty for PWR Spent Nuclear Fuel. CAL-DSU-NU-000001 REV A. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2002).

J. M. Scaglione. Three Mile Island Unit 1 Radiochemical Assay Comparisons to SAS2H Calculations. CAL-UDC-NU-000011 REV A. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (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 ofFixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit," Nucl. Technol. 139, 91-126 (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. 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11–15, 2001, Reno, NV.

 

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).

C. W. Connell and J. M. Scaglione. Summary Report of Two-Dimensional Analysis of Radiochemical Assay Samples. TDR-UDC-NU-000006 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2001).

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

 

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

 

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

 

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

 

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

 

I. C. Gauld, Limited Burnup Credit in Criticality Safety Analysis: A Comparison of ISG-8 and Current International Practice, NUREG/CR-6702 (ORNL/TM-2000/72), 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. 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV, November 11–15, 2001. 

 

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. 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV, November 11–15, 2001.

 

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

 

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. 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV, November 11-15, 2001.

 

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. 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV, November 11–15, 2001.

 

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

 

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, Reno, NV, November 11–15, 2001.

 

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

 

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.

 

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. 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV, November 11–15, 2001.

 

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. U.S. NRC 28th 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. 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. 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. 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. 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. 13th International Symposium on the Packaging and Transportation of Radioactive Material (PATRAM2001), Chicago, IL, September 3–7, 2001.

 

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. 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV, November 11–15, 2001. 

 

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

 

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

 

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

J. M. Scaglione. PWR Assembly End-Effect Reactivity Evaluation. CAL-UDC-NU-000006 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2001).

J. M. Scaglione. 21 PWR Waste Package Variable Spent Nuclear Fuel Loading Evaluation. CAL-UDC-NU-000008 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2001).

J. M. Scaglione. PWR Depletion Parameter Sensitivity Evaluation. CAL-UDC-NU-000009 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (2001).

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

 

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. 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. 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, Oak Ridge, Tenn., 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, Proc. Technical Committee Meeting, IAEA, Vienna, Austria, July 10-14, 2000.

 

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, Oak Ridge, Tenn., March 2000.

J. C. Wagner and M. D. DeHart, "Investigation of BWR Depletion Calculations with SAS2H," Trans. Am. Nucl. Soc. 82, 173-176, June 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, Oak Ridge, Tenn., 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, Versailles, France, September 20–24, 1999.

 

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. Sixth International Conference on Nuclear Criticality Safety, Versailles, France, September 20–24, 1999.

 

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, Oak Ridge, Tenn., 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. Sixth International Conference on Nuclear Criticality Safety, Versailles, France, September 20–24, 1999.

 

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. Sixth International Conference on Nuclear Criticality, Versailles, France, September 20–24, 1999.

 

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, Oak Ridge, Tenn., 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).

 

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).

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. Sixth International Conference on Nuclear Criticality Safety, Versailles, France, September 20–24, 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. Sixth International Conference on Nuclear Criticality Safety, Versailles, France, September 20-24, 1999.

 

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

 

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. Sixth International Conference on Nuclear Criticality Safety, Versailles, France, September 20-24, 1999.

 

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

D. A. Salmon and J. M. Scaglione. CRC Reactivity Calculations for Quad Cities Unit 2. B00000000-01717-0210-00010 REV 01. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (1999).

J. M. Scaglione. Rod Consolidation Waste Package Criticality Calculations. B00000000-01717-0210-00043 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (1999).

J. M. Scaglione. Waste Package, LCE, CRC, and Radiochemical Assay Comparison Evaluation. B00000000-01717-0210-00107 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (1999).

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. Sixth International Conference on Nuclear Criticality Safety, Versailles, France, September 20–24, 1999.

 

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. Sixth International Conference on Nuclear Criticality Safety, Versailles, France, September 20–24, 1999.

 

T. E. Valentine, Review of Subcritical Source-Driven Noise Analysis Measurements, ORNL/TM-1999/288, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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, EPRI 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, R. N. Blomquist, C. G. Stenberg, and C. Jammes, Evaluation of Fission Product Worth Margins in PWR Spent Nuclear Fuel Burnup Credit Calculations, ANL-FRA-1998-1, Argonne National Laboratory, Argonne, IL, 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., October 1998.

 

J. C. Neuber, "Burnup Credit Applications to PWR and BWR Fuel Assembly Wet Storage Systems," Vol. 1, pp. 631–638 in Proc. 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).

J. M. Scaglione, CRC Depletion Calculations for Crystal River Unit 3. B00000000-01717-0210-00001 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (1998).

J. M. Scaglione, CRC Reactivity Calculations for Crystal River Unit 3. B00000000-01717-0210-00002 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (1998).

J. M. Scaglione, Sequoyah Unit 2 CRC Depletion Calculations. B00000000-01717-0210-00005 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (1998).

J. M. Scaglione. CRC Reactivity Calculations for Sequoyah Unit 2. B00000000-01717-0210-00006 REV 00. Las Vegas, Nevada: Office of Civilian Radioactive Waste Management (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. Eight International High Level Waste Management Conference, Las Vegas, NV, May 11–14, 1998.

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, End Effect Keff Bias Curve for Actinide-Only Burnup Credit Casks, DOE/RW-00134, U.S. Department of Energy, 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.

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.

J. S. Tulenko, G. Schoessow, and J. M. Scaglione, "A New Fuel Rod Design for Ultra High Burnup Cycles," ICONE 5: Proc. 5th International Conference on Nuclear Engineering, Nice, France, May 26-30, 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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 10 – 5 C 17 in Proc. Fifth International Conference on Nuclear Criticality Safety, 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. 1C 3 – 1B C 10 in Proc. 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, Oak Ridge, Tenn., , 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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, Oak Ridge, Tenn., 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. Fifth International Conference on Nuclear Criticality, Albuquerque, NM, September 17–21, 1995.

 

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, Oak Ridge, Tenn., 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. 1994 Topical Meeting on Advances in Reactor Physics, Knoxville, TN, April 11–15, 1994.

 

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. Fifth Annual International Conference on High Level Radioactive Waste Management, Las Vegas, NV, May 22–26, 1994.

 

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. 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. International Conference on Nuclear Criticality Safety, Christ Church, Oxford, United Kingdom, September 9–13, 1991.

 

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. International Conference on Nuclear Criticality Safety, Christ Church, Oxford, United Kingdom, September 9–13, 1991.

 

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 3rd International Conference on Nuclear Fuel Reprocessing Waste Management, Sendai, Japan, April 14–18, 1991.

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. 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. International Topical Meeting on Safety Margins in Criticality Safety, San Francisco, CA, November 26–30, 1989.

 

C. V. Parks, "An Approach for Verifying Analysis Techniques Applicable to the Burnup Credit Technical Issue," pp. 189–196 in Proc. 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. 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).

 

S. P. Cerne, O. W. Hermann, and R. M. Westfall, Reactivity and Isotopic Composition of Spent PWR Fuel as a Function of Initial Enrichment, Burnup, and Cooling Time, ORNL/CSD/TM-244, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 1987.

 

Characteristics of Spent Fuel, High-Level Waste, and Other Radioactive Wastes Which May Require Long-Term Isolation, DOE/RW-0184, December 1987.

 

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, Tokyo, Japan, October 19–23, 1987.

 

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. Topical Meeting on Criticality Safety in the Storage of Fissile Material, Jackson, WY, September 8–11, 1985.

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 2nd 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.