Reactor and Nuclear Systems Division

Kevin Clarno

Kevin T. Clarno

R&D Staff
Design, Safety and Simulation Integration
Reactor and Nuclear Systems Division
Nuclear Science and Engineering Directorate
Oak Ridge National Laboratory
P.O. Box 2008, Bldg. 5700
Oak Ridge, TN 37831-6170
Phone: 865.241.1894
Fax: 865.574.3527
clarnokt@ornl.gov

Curriculum Vitae

Education

  • Ph.D., Nuclear Engineering, Texas A&M University, College Station, TX
  • M.S., Nuclear Engineering, Texas A&M University, College Station, TX
  • B.S., Nuclear Engineering, Massachusetts Institute of Technology, Cambridge, MA

Publications

2014

A. Phillippe, K. T. Clarno, et al., "A Validation Study of Pin Heat Transfer for MOX Fuel Based on the IFA-597 Experiments," Nucl. Sci. Eng. . Accepted and in production for target issue: 177(3), (2014).

A. Phillippe, K. T. Clarno, et al., "A Validation Study of Pin Heat Transfer for UO2 Fuel Based on the IFA-432 Experiments," Nucl. Sci. Eng. . Accepted and in production for target issue: 177(3), (2014).

2013

M. Piro, J. Banfield, K. T. Clarno, et al., "Coupled thermochemical, isotopic evolution and heat transfer simulations in highly irradiated UO2 nuclear fuel," J. Nucl. Matl. . 441, 240-251, 2013.

2012

K. T. Clarno et al., "The AMP (Advanced MultiPhysics) Nuclear Fuel Performance Code," Nucl. Eng. Design 252(1), 108-120, November 2012.

A. M. Phillippe, L. J. Ott, K. T. Clarno, and J. E. Banfield, Analysis of the IFA-432, IFA-597, and IFA-597 MOX Fuel Performance Experiments by FRAPCON-3,4, ORNL/TM-2012/195, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2012.

B. Philip, K. T. Clarno, R. S. Sampath, M. A. Berrill, S. Allu, G. Dilts, and P. Barai, "The Advanced Multi-Physics (AMP) Package with an Application to Fuel Assemblies in Nuclear Reactors," 2012 SIAM Annual Meeting, Minneapolis, MN, July 9-13, 2012.

K. T. Clarno, S. P. Hamilton, B. Philip, R. Sampath, S. Allu, M. A. Berrill, P. Barai, and J. E. Banfield, "Integrated Radiation Transport and Thermo-Mechanics Simulation of a PWR Assembly," Trans. Am. Nucl. Soc. 106, 2012.

B. Philip, R. S. Sampath, S. P. Hamilton, M. A. Berrill, S. Allu, and K. T. Clarno, "Computational Approach to Nuclear Fuel Assembly Simulation," Trans. Am. Nucl. Soc. 106, 2012.

M. H. Piro, J. E. Banfield, S. Simunovic, T. M. Besmann, and K. T. Clarno, "Computational Thermodynamics in the Advanced Multi-Physics Code," Trans. Am. Nucl. Soc. 106, 1384-1386, 2012.

J. E. Banfield, K. T. Clarno, S. P. Hamilton, G. I. Maldonado, B. Philip, and M. L. Baird, "Benchmarking of Software and Methods for Use in Transient Multidimensional Fuel Performance with Spatial Reactor Kinetics," ICAPP '12, Chicago, IL, June 24-28, 2012.

M. H. Piro, S. Simunovic, T. M. Besmann, and K. T. Clarno, “Coupling Thermodynamic Computations with Multi-Physics Nuclear Fuel Codes,” Computer Coupling of Phase Diagrams and Thermochemistry (CALPHAD), Berkeley, CA, June 3-8, 2012.

S. Hamilton, K. Clarno, B. Philip, M. Berrill, R. Sampath, and S. Allu, "Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations," PHYSOR 2012--Advances in Reactor Physics--Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2012).

S. Hamilton, K. Clarno, B. Philip, R. Sampath, M. Berrill, S. Allu, M. Baird, and J. Banfield, "Coupled Radiation Transport and Thermomechanics Using the AMP and Denovo Codes," Twelfth Copper Mountain Conference on Iterative Methods, Copper Mountain, CO, March 25-30, 2012.

B. Philip, K. Clarno, R. Sampath, M. Berrill, S. Allu, and G. Dilts, "The Advanced Multi-Physics (AMP Package), Twelfth Copper Mountain Conference on Iterative Methods, Copper Mountain, CO, March 25-30, 2012.

B. Philip, K. Clarno, R. Sampath, M. Berrill, and S. Allu, "A Jacobian Free Newton Krylov Method with Multilevel Block Preconditioning for Multi-Domain Quasistatic Thermomechanics," Twelfth Copper Mountain Conference on Iterative Methods, Copper Mountain, CO, March 25-30, 2012.

K. T. Clarno and R. L. Howard, Problem Specification for FY12 Modeling of Used Nuclear Fuel during Extended Storage, ORNL/TM-2012/80, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2012.

K. T. Clarno et al., Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations, ORNL/TM-2012/33, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2012.

2011

G. Yesilyurt, K. T. Clarno, T. M. Evans, G. G. Davidson, and P. B. Fox, "A C5 Benchmark Problem with Discrete Ordinate Radiation Transport Code DENOVO," Nucl. Technol. 176(2), 274-283, November 2011.

S. P. Hamilton and K. T. Clarno, "Mathematical Framework for the Coupling of the AMP and Denovo Codes," Trans. Am. Nucl. Soc. 105, 515-517 (2011).

J. E. Banfield et al., "Quasi-Static Validation of the AMP Nuclear Fuel Performance Code," Trans. Am. Nucl. Soc. 104, June 2011.

P. Barai et al., "Strain-Based Continuum Damage Models for Nuclear Fuels," Trans. Am. Nucl. Soc. 104, June 2011.

G. Yesilyurt, K. T. Clarno, I. C. Gauld, and J. D. Galloway, "Modular ORIGEN-S for Multi-Physics Code Systems," Proceedings of the Mathematics and Computations Division of the American Nuclear Society Topical Meeting(M&C-2011), May 2011.

2010

T. M. Evans, K. T. Clarno, and J. E. Morel, "A Transport Acceleration Scheme for Multigroup Discrete Ordinates with Upscattering," Nucl. Sci. Eng. 165(3), 292-304 (2010).

T. M. Evans, A. S. Stafford, and K. T. Clarno, "Denovo-A New Three-Dimensional Parallel Discrete Ordinates Code in SCALE," Nucl. Technol. 171(2), 171-200 (2010).

B. Philip, K. T. Clarno, and W. K. Cochran, Software Design Document for the AMP Nuclear Fuel Performance Code, ORNL/TM-2010/34, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2010.

R. C. Schmidt, K. Belcourt, K. T. Clarno et al., "Foundational Development of an Advanced Nuclear Reactor Integrated Safety Code," SAND2010-0878, Sandia National Laboratories, Albuquerque, New Mexico, 2010.

S. Allu et al., "Initial Validation of the AMP Nuclear Fuel Performance Code," Trans. Am. Nucl. Soc. 103, November 2010.

G. G. Davidson et al., "Massively Parallel Solutions to the K-Eigenvalue Problem," Trans. Am. Nucl. Soc., 103, November 2010.

J. D. Galloway et al., "Generalized Isotopic Tracking Capabilities Within the 3-D BWR Nodal Simulator NESTLE," Trans. Am. Nucl. Soc. 103, November 2010.

2009

K. T. Clarno and J. P. Renier, Test Problem #3: 2009 Three-Dimensional Boiling Water Reactor Simulations, ORNL/TM-2009/250, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2009.

T. M. Evans and K. T. Clarno, C++ Coding Standards for the AMP Project, ORNL/TM-2009/240, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2009.

K. T. Clarno, J. A. Turner, and G. A. Hansen, Roadmap to an Engineering-Scale Nuclear Fuel Performance and Safety Code, ORNL/TM-2009/233, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2009.

G. I. Maldonado et al., "Integration of the NESTLE Core Simulator within SCALE," Trans. Am. Nucl. Soc. 100, June 2009.

2008

D. F. Williams and K. T. Clarno, "Evaluation of Salt Coolants for Reactor Applications," Nucl. Technol. 163(3), 330-343 (2008).

Z. Zhong, K. T. Clarno, T. J. Downar, and M. D. DeHart, "Implementation of a Two-Level Coarse Mesh Finite Difference Acceleration of an Arbitrary Geometry Two-Dimensional Discrete-Ordinates Transport Method," Nucl. Sci. Eng. 158(3), 289-298 (2008).

Y. Wang et al., "Progress in the Integration of the 2D DG-FEM Sn Transport Sovler Xuthus into SCALE," Trans. Am. Nucl. Soc. 99, November 2008.

T. Greifenkamp, K. T. Clarno, and J. C. Gehin, "Effect of Fuel Temperature Profile on Eigenvalue Calculations," Proceedings of the 2008 American Nuclear Society Student Conference, February 2008.

K. T. Clarno, "Parallel (Sn) Transport Algorithm in NEWTRNX," Proceedings of Reactor Physics Division of the American Nuclear Society Topical Meeting (PHYSOR-2008), September 2008.

S. A. Vilkomir, W. T. Swain, J. H. Poore, and K. T. Clarno, "Modeling Input Space for Testing Scientific Computational Software: A Case Study," Proceedings of the International Conference on Computational Science (ICCS-2008), June 2008.

2007

B. Ganapol, K. T. Clarno, and S. P. Hamilton, "An Embedded Semi-Analytical Benchmark with Iterative Interpolation for Neutron Transport Methods Verification," Proceedings of the Joint Supercomputing in Nuclear Applications and Mathematics and Computations Division of the American Nuclear Society Topical Meeting (SNA/M&C-2007), April 2007.

D. T. Ingersoll, K. T. Clarno et al., Trade Studies for the Liquid-Salt-Cooled Very High-Temperature Reactor: Fiscal Year 2006 Progress Report, ORNL/TM-2006/140, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2007.

K. T. Clarno, "Implementation of Generalized Coarse-Mesh Rebalance in NEWTRNX for Acceleration of Parallel Block Jacobi Transport," Trans. Am. Nucl. Soc. 97, November 2007.

S. R. Johnson and K. T. Clarno, "Implementation of Transport Synthetic Acceleration in NEWTRNX," Trans. Am. Nucl. Soc. 97, November 2007.

S. P. Hamilton, C. R. E. de Oliveira, and K. T. Clarno, "Implementation of Time-Dependent Transport in NEWTRNX," Trans. Am. Nucl. Soc. 97, November 2007.

S. R. Johnson and K. T. Clarno, "Comparison of SCALE and MCNP Results for Computational Pebble Bed Benchmarks," Trans. Am. Nucl. Soc. 96, June 2007.

2006

R. T. Primm III, K. T. Clarno et al., Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for the FY 2006, ORNL/TM-2006/136, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2006.

D. F. Williams, L. M. Toth, and K. T. Clarno, Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR), ORNL/TM-2006/12, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2006.

M. L. Williams, J. C. Gehin, and K. T. Clarno, "Sensitivity Analysis of Reactivity Responses Using One-Dimensional Discrete Ordinates and Three-Dimensional Monte Carlo Methods," Proceedings of Reactor Physics Division of the American Nuclear Society Topical Meeting (PHYSOR-2006), September 2006.

Z. Zhong, T. J. Downar, M. D. DeHart, and K. T. Clarno, "Coarse Mesh Finite Difference Acceleration in the Two-Dimensional Discrete Ordinates Transport Calculation," Proceedings of Reactor Physics Division of the American Nuclear Society Topical Meeting (PHYSOR-2006), September 2006.

K. T. Clarno and J. C. Gehin, "Physics Analysis of the LS-VHTR: Salt Coolant and Fuel Block Design," Proceedings of Reactor Physics Division of the American Nuclear Society Topical Meeting (PHYSOR-2006), September 2006.

K. T. Clarno, V. F. de Almeida, E. D’Azevedo, C. R. E. de Oliveira, and S. P. Hamilton, "GNES-R: Global Nuclear Energy Simulator for Reactors, Task 1: High-Fidelity Neutron Transport," Proceedings of Reactor Physics Division of the American Nuclear Society Topical Meeting (PHYSOR-2006), September 2006.

D. F. Williams and K. T. Clarno, "Salt Selection for the LS-VHTR," Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP 2006), June 2006.

2005

K. T. Clarno and M. L. Adams, "Capturing the Effects of Unlike Neighbors in Single-Assembly Calculations," Nucl. Sci. Eng. 149(2), 182-196 (2005).

D. T. Ingersoll, K. T. Clarno, C. W. Forsberg, J. C. Gehin, R. W. Christensen, C. B. Davis, G. L. Hawkes, and J. W. Sterbentz, T. K. Kim, T. A. Taiwo, and W. S. Yang, Status of Physics and Safety Analyses for the Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR), ORNL/TM-2005/218, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2005.

C. W. Forsberg and K. T. Clarno, "The Advanced High-Temperature Reactor (AHTR): Flux Distribution and Dosimetry," Proceedings of the International Symposium on Reactor Dosimetry (ISRD-2005), May 2005.

K. T. Clarno, C. W. Forsberg, and J. C. Gehin, "Physics Analysis of Coolant Voiding in the Advanced High Temperature Reactor," Trans. Am. Nucl. Soc. 93, November 2005.

K. T. Clarno et al., "Code-To-Code Benchmark of Coolant Void Reactivity (CVR) in the ACR-700 Reactor," Trans. Am. Nucl. Soc. 93, November 2005.

2004

K. T. Clarno, "An Advanced Nuclear Reactor Analysis Methodology for Heterogeneous Cores," Texas A&M University, Department of Nuclear Engineering, Ph.D. Dissertation (M. L. Adams, advisor), August 2004.

2003

K. T. Clarno and Y. A. Hassan, "Development of a RELAP5-3D Multi-dimensional Model of a VVER- 1000 NPP for Analysis of a LB LOCA," Nucl. Technol. 141(2), 142-156 (2003).

K. T. Clarno, "TXYPL - TXY with General Anisotropic Scattering," Bechtel Bettis Atomic Power Laboratory Internal Letter, B-MER(ACRE)-59 and Attachment, July 2003.

K. T. Clarno and M. L. Adams, "Capturing the Effects of Unlike Neighbors in Single-Assembly Calculations," Proceedings of the Mathematics and Computations Division of the American Nuclear Society Topical Meeting (M&C 2003), April 2003.

K. T. Clarno and M. L. Adams, "Recent Improvements in Boundary Conditions for Single-Assembly Calculations," Trans. Am. Nucl. Soc. 89, November 2003.

2002

K. T. Clarno and M. L. Adams, "Improved Boundary Conditions for Assembly-Level Transport Codes," Proceedings of Reactor Physics Division of the American Nuclear Society Topical Meeting (PHYSOR-2002), September 2002.

2001

K. T. Clarno, "Development of a RELAP5-3D Three-dimensional Model of a VVER-1000 Nuclear Power Plant for Analysis of a Large-Break Loss-of-Coolant Accident," Texas A&M University, Department of Nuclear Engineering, M.S. Thesis (Y.A. Hassan, advisor), August 2001.

K. T. Clarno and Y. A. Hassan, "Development of a RELAP5-3D Three-dimensional Model of a VVER-1000 Nuclear Power Plant for Analysis of a Large-Break Loss-of-Coolant Accident," Trans. Am. Nucl. Soc. 85, November 2001.

1999

K. T. Clarno, "Composition Optimization of Thorium-Uranium Pressurized Water Reactor Cores," Massachusetts Institute of Technology, Department of Nuclear Engineering, S.B. Thesis (M.J. Driscoll, advisor), June 1999.