Skip to main content

Criticality Safety

2022 Publications:

Travis M. Greene and William J. Marshall, SCALE 6.2.4 Validation: Nuclear Criticality SafetyORNL/TM-2020/1500/v2, UT-Battelle, LLC, Oak Ridge National Laboratory (November 2022).

A. M. Shaw and J. B. Clarity, Impacts of LEU+ and ATF on Fresh Fuel Storage Criticality Safety, ORNL/TM-2021/2330,  UT-Battelle, LLC, Oak Ridge National Laboratory (February 2022).

2020 Publications:

Kursat Bekar, Justin Clarity, Mathieu Dupont, Robert Lefebvre, William Marshall, and Ellen Saylor, KENO-VI Primer: Performing Calculations using SCALE’s Criticality Safety Analysis Sequence (CSAS6) with Fulcrum, ORNL/TM-2020/1601, UT-Battelle, LLC, Oak Ridge National Laboratory (December 2020). [supporting files]

Kursat Bekar, Justin Clarity, Mathieu Dupont, Robert Lefebvre, William Marshall, and Ellen Saylor, KENO V.a Primer: Performing Calculations using SCALE’s Criticality Safety Analysis Sequence (CSAS5) with Fulcrum, ORNL/TM-2020/1664, UT-Battelle, LLC, Oak Ridge National Laboratory (December 2020) .[supporting files]

Robert Hall, B.J. Marshall, and William A. Wieselquist, Assessment of Existing Transportation Packages for Use with HALEU, ORNL/TM-2020/1725, UT-Battelle, LLC, Oak Ridge National Laboratory (September 2020). [supporting files]

Dongli Huang, Ugur Mertyurek, and Hany Abdel-Khalik, "Verification of the Sensitivity and Uncertainty-based criticality Safety Validation Techniques: ORNL’s SCALE Case Study," Nuclear Engineering and Design, 361, 10571 (February 2020).

 

Prior Year Publications:

I. Duhamel, J. L. Alwin, F. B. Brown, M. E. Rising, K. Y. Spencer, D. Heinrichs, S. Kim, W. J. Marshall, and E. M. Saylor, “International Criticality Benchmark Comparison for Nuclear Data Validation,” Transactions of the American Nuclear Society, 121, 873–876 (November 2019). [pdf]

B. T. Rearden, “Some Innovations of Dr. Mark Williams for the Practical Application of Sensitivity and Uncertainty Analysis to Reactor Analysis and Criticality Safety,” Transactions of the American Nuclear Society, 121, 1479–1483 (November 2019). [pdf]

W. A. Wieselquist, “Recent SCALE Activities Within the Nuclear Criticality Safety Program,” Transactions of the American Nuclear Society, 121, 877–880 (November 2019).  

C. M. Perfetti and B. T. Rearden, “Estimating Code Biases for Criticality Safety Applications with Few Relevant Benchmarks,” Nuclear Science Engineering 193(10), 1090–1128 (October 2019). 

W. J. Marshall, E. M. Saylor, A. M. Holcomb, D. Wiarda, and T. M. Greene, “Validation of KENO V.a and KENO-VI in SCALE 6.3 Beta 3 Using ENDF/B-VII.1 and ENDF/B-VIII Libraries,” Proceedings of 11th International Conference on Nuclear Criticality Safety (ICNC 2019), September 15–20, 2019, Paris, France. 

W. J. Marshall, B. J. Ade, I. C. Gauld, G. Ilas, U. Mertyurek, J. B. Clarity, G. Radulescu, B. R. Betzler, S. M. Bowman, and J. S. Martinez-Gonzalez, “Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory, Proceedings of 11th International Conference on Nuclear Criticality Safety 2019 ICNC 2019), September 15–20, 2019, Paris, France.

M. Stuke, A. Hoefer, O. Buss, M. Chernykh, G. Dobson, J. Dyrda, T. Ivanova, N. Leclaire, W. J. Marshall, D. Mennerdahl, B. T. Rearden, P. Smith, F. Sommer, and S. Tittelbach, “UACSA Phase IV: Role of Integral Experiment Covariance Data for Criticality Safety Validation – Summary of Selected Results,” Proceedings of 11th International Conference on Nuclear Criticality Safety 2019 (ICNC 2019), September 15–20, 2019, Paris, France.

B. T. Rearden, W. J. Marshall, J. B. Clarity, A. M. Holcomb, F. Bostelmann, and J. M. Scaglione, “Initial Investigations of the Criticality Safety Validation Basis for HA-LEU Transportation,” Transactions of the American Nuclear Society, 120, 517–520 (June 2019).

W. J. Marshall, J. B. Clarity, and S. M. Bowman, “Validation of keff Calculations for Extended BWR Burnup Credit Calculations,” Transactions of the American Nuclear Society, 120, 554–557 (June 2019). 

W. J. Marshall, J. B. Clarity, and S. M. Bowman, Validation of keff Calculations for Extended BWR Burnup Credit, NUREG/CR-7252 (ORNL/TM-2018/797), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, (December 2018). 

I. Gauld and U. Mertyurek, Margins for Uncertainty in the Predicted Spent Fuel Isotopic Inventories for BWR Burnup Credit, NUREG/CR-7251 (ORNL/TM-2018/782), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, (December 2018). 

E. M. Saylor, W. J. Marshall, J. B. Clarity, Z. J. Clifton, and B. T. Rearden, Criticality Safety Validation of SCALE 6.2.2ORNL/TM-2018/884, UT-Battelle, LLC, Oak Ridge National Laboratory (September 2018).

B. J. Ade, B. J. Marshall, G. Ilas, B. R. Betzler, and S. M. Bowman, Impact of Reactor Operating Parameters on Extended BWR Burnup Credit, NUREG/CR-7240 (ORNL/TM - 2017/46), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (January 2018). 

E. M. Saylor, W. J. Marshall, Z. J. Clifton, J. B. Clarity, and B. T. Rearden, “Validation of KENO V.A and KENO-VI in SCALE 6.2.2 Using ENDF/B-VII.0 and ENDF/B-VII.1 Libraries,” Transactions of the American Nuclear Society118, 571–574 (2018). 

G. Ilas, B. Betzler, and B. Ade, “Impact of Reactor Operating Parameters on Cask Reactivity in BWR Burnup Credit”, Proceedings of the 18th International Symposium on the  Packaging and Transportation of Radioactive Materials  PATRAM 2016, September 1822, 2016, Kobe, Japan. [pdf]

B. T. Rearden, K. B. Bekar, C. Celik, K. T. Clarno, M. E. Dunn, S. W. D. Hart, A. M. Ibrahim, S. R. Johnson, B. R. Langley, J. P. Lefebvre, R. A. Lefebvre, W. J. Marshall, U. Mertyurek, D. E. Mueller, D. E. Peplow, C. M. Perfetti, L. M. Petrie, Jr., A. B. Thompson, D. Wiarda, W. A. Wieselquist, and M. L. Williams, "Criticality Safety Enhancements For Scale 6.2 And Beyond," Proceedings of International Cooperation in Nuclear Criticality Safety (ICNC 2015), pp. 12551269, September 1317, 2015, Charlotte, North Carolina.

B. T. Rearden, L. M. Petrie, D. E. Peplow, K. B. Bekar, D. Wiarda, C. Celik, C. M. Perfetti, A. M. Ibrahim, S. W. D. Hart, M. E. Dunn, and W. J. Marshall, “Monte Carlo Capabilities of the SCALE Code System,” Annals of Nuclear Energy, 82, 130–141 (2015).  

B. J. Marshall, B. J. Ade, S. M. Bowman, I. C. Gauld, G. Ilas, U. Mertyurek, and G. Radulescu, Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems, NUREG/CR-7194, U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (April 2015). 

G. Radulescu, I. C. Gauld, G. Ilas, and J. C. Wagner, “Approach for validating actinide and fission product compositions for burnup credit criticality safety analyses,” Nuclear Technology, 188 (2), 154171 (2014).

B. T. Rearden, L. M. Petrie, D. E. Peplow, K. B. Bekar, D. Wiarda, C. Celik, C. M. Perfetti, M. E. Dunn and S. W. D. Hart, “Enhancements In Continuous-Energy Monte Carlo Capabilities for SCALE 6.2,”  Proceedings of PHYSOR 2014, September 28–October 3, 2014, Kyoto, Japan.

W. A. Wieselquist, K. S. Kim, G. Ilas, and I. C. Gauld, “Comparison of burnup credit uncertainty quantification methods,” Proceedings of Topical Meeting on Nuclear Criticality Safety (NCSD 2013,) September 29–October 3, 2013, Wilmington, North Carolina. [pdf]

T. M. Miller and D. E. Peplow, “Corrected User Guidance to Perform Three-Dimensional Criticality Accident Alarm System Modeling with SCALE,” Transactions of the American Nuclear Society 108, 498–501 (2013).

K. B. Bekar, C. Celik, D. Wiarda, D. E. Peplow, B. T. Rearden, and M. E. Dunn, “Enhancements in Continuous-Energy Monte Carlo Capabilities in SCALE,” Proceedings of Topical Meeting on Nuclear Criticality Safety (NCSD 2013,) September 29–October 3, 2013, Wilmington, North Carolina. [pdf]

T. M. Miller and D. E. Peplow, “Guidance Detailing Methods to Calculate Criticality Accident Alarm Detector Response and Coverage,” Proceedings of Topical Meeting on Nuclear Criticality Safety (NCSD 2013,) September 29–October 3, 2013, Wilmington, North Carolina. [pdf]

B. T. Rearden, M. E. Dunn, D. Wiarda, C. Celik, K. Bekar, M. L. Williams, D. E. Peplow, C. M. Perfetti, I. C. Gauld, W. A. Wieselquist, J. P. Lefebvre, R. A. Lefebvre, F. Havlůj, S. E. Skutnik, and K. J. Dugan, “Overview of SCALE 6.2,” Proceedings of Topical Meeting on Nuclear Criticality Safety (NCSD 2013,) September 29–October 3, 2013, Wilmington, North Carolina. [pdf]

B. T. Rearden, M. E. Dunn, D. Wiarda, C. Celik, K. B. Bekar, M. L. Williams, D. E. Peplow, C. M. Perfetti, J. P. Lefebvre, F. Havluj, and K. J. Dugan, “SCALE and AMPX Advancements to Support NCS Applications,” Transactions of the American Nuclear Society 109, 907–910 (2013).

T. M. Miller and D. E. Peplow, Guide to Performing Computational Analysis of Criticality Accident Alarm Systems, ORNL/TM-2013/211, UT-Battelle, LLC, Oak Ridge National Laboratory (August 2013). [supporting files]

W. J. Marshall and B.T. Rearden, Criticality Safety Validation of SCALE 6.1ORNL/TM-2011/450, UT-Battelle, LLC, Oak Ridge National Laboratory (January 2013 Revised). [supporting files]

D. E. Peplow and L. L. Wetzel, “Methods for Detector Placement and Analysis of Criticality Accident Alarm System,” Transactions of the American Nuclear Society 106, 497–500 (June 2012). [pdf]

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

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), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, (April 2012). 

B. T. Rearden, L. M. Petrie, D. E. Peplow, M. A. Jessee, D. Wiarda, M. L. Williams, R. A. Lefebvre, J. P. Lefebvre, I. C. Gauld, and S. Goluoglu, “Enhancements in SCALE 6.1,” Proceedings of PHYSOR 2012, April 2012. [pdf]

D. E. Peplow and L. M. Petrie, Jr., “Criticality Accident Alarm System Modeling Made Easy With SCALE 6.1,” Transactions of the American Nuclear Society 102, 297–299 (2010).

D. E. Peplow and L. M. Petrie, Jr., “Criticality Accident Alarm System Modeling With SCALE,” Proceedings of the 2009 International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics (M&C 2009), May 3–7, 2009, Saratoga Springs, New York. [pdf]

D. F. Hollenbach and P. B. Fox, CENTRM Validation, ORNL/TM-2004/66, UT-Battelle, LLC, Oak Ridge National Laboratory (May 2005).   [supporting files]

P. B. Fox and D. F. Hollenbach, KENO-VI ValidationORNL/TM-2004/60, UT-Battelle, LLC, Oak Ridge National Laboratory (May 2005).   [supporting files]

P. B. Fox and L. M. Petrie, Validation and Comparison of KENO V.a and KENO-VIORNL/TM-2001/110, UT-Battelle, LLC, Oak Ridge National Laboratory (May 2002).

S. M. Bowman, W. C. Jordan, J. F. Mincey, C. V. Parks, and L. M. Petrie, Experience with the SCALE Criticality Safety Cross-Section LibrariesNUREG/CR-6686 (ORNL/TM-1999/322), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (October 2000).

J. J. Lichtenwalter, S. M. Bowman, M. D. DeHart, and C. M. Hopper, Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage PackagesNUREG/CR-6361 (ORNL/TM-13211), U.S. Nuclear Regulatory Commission, UT-Battelle, LLC, Oak Ridge National Laboratory (March 1997)  [supporting files]