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Publications

Peer-reviewed journal publications:


N.T. Shoman and S. E. Skutnik, “Development of modern CANDU PHWR cross-section libraries for SCALE,” Nuclear Engineering and Design, 302, 56–67 (June 2016) . (doi:10.1016/j.nucengdes.2016.04.007)


S.E. Skutnik and D. R. Davis, “Characterization of the non-uniqueness of used nuclear fuel burnup signatures through a Mesh-Adaptive Direct Search,” Nuclear Instruments and Methods in Physics Research A, 817(1), pp. 7-18, May 2016. (doi:10.1016/j.nima.2016.02.007)


K. Ottinger and G. I. Maldonado, “SMR Fuel Cycle Optimization Using LWROpt,” Under Review, ASME Journal of Nuclear Engineering and Radiation Science, May 2016 (NERS-16-1047).


S.W.D. Hart, C. Celik, G. I. Maldonado, L. Leal, “Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code,” Annals of Nuclear Energy, 88, 49-56 (Feb. 2016).(doi:10.1016/j.anucene.2015.10.011)


K. Ottinger and G. I. Maldonado, “BWROPT: A multi-cycle BWR fuel cycle optimization code,” Nuclear Engineering and Design, 291, 236-243 (Sep. 2015).(doi:10.1016/j.nucengdes.2015.05.029)


N. George, G.I. Maldonado, K. Terrani, A. Godfrey, J.C. Gehin, J. Powers, and A. Worrall, “Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts In Pressurized Water Reactors,” Annals of Nuclear Energy, 75, 703-712 (Jan. 2015). (doi:10.1016/j.anucene.2014.09.005)


N. George, G.I. Maldonado, K. Terrani, J. Powers, and A. Worrall, “Neutronics Studies of Uranium-bearing Fully Ceramic Microencapsulated Fuel for Pressurized Water Reactors,” Nuclear Technology, 188 (3), p. 238-251 (Dec. 2014). (doi:10.13182/NT14-3 )


C. Gentry, G.I. Maldonado, A. Godfrey, K. Terrani, J.C. Gehin, and J. Powers, “A Neutronic Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Pu/Np Burning in PWRs,” Nuclear Technology, 186, 60-75 (Apr. 2014) (doi:10.13182/NT13-75 )

Peer-reviewed conference publications


S.E. Skutnik and N. T. Shoman, “Re-Evaluation of the 154Eu thermal capture cross-section based on spent fuel benchmarking studies,” presented at PHYSOR 2016, Sun Valley, ID, May 1-5, 2016


J. Littell, A. Worrall, S. Skutnik, and E. Sunny, “Assessment and Benchmarking with ORION and CYCLUS for US fuel cycle options,” presented at PHYSOR 2016, Sun Valley, ID, May 1-5, 2016


J. R. Knowles, S. E. Skutnik, D. C. Glasgow, and R. J. Kapsimalis, “A generalized method for fissile mass characterization using short-lived fission product gamma measurements,” presented at PHYSOR 2016, Sun Valley, ID, May 1-5, 2016


N.C. Sly, S. E. Skutnik, and W. A. Wieselquist, “Portable reactor data library interpolation via self-describing ORIGEN libraries,” presented at PHYSOR 2016, Sun Valley, ID, May 1-5, 2016


S. E. Skutnik, M. L. Williams, R. A. Lefebvre, “ORIGAMI: A New Interface for Fuel Assembly Characterization with ORIGEN,” 2015 International High-Level Radioactive Waste Management Conference, pp. 418-425, Charleston, SC, April 12-16, 2015


N. A. Earle and S. E. Skutnik, “Contamination of Zirconium Metal by Cadmium Dissolved in Molten LiCl-KCl Salt,” 2015 International High-Level Radioactive Waste Management Conference, pp. 160-165, Charleston, SC, April 12-16, 2015


N.P. Luciano and G.I. Maldonado, “Verification of the Pin Power Reconstruction Method in NESTLE,” Proc. TOP FUEL 2016, Boise, ID, September 11-16, 2016.


N.P. Luciano, G.I. Maldonado, I. Gauld, “Modeling and Simulation of an Operational VVER-1000 Benchmark with NESTLE,” Proc. 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17-20, 2016.


T.A. Eckleberry and G.I. Maldonado, “Reactivity Assessment of Enhanced Accident Tolerant Claddings in a Modern PWR,” PHYSOR 2016, Sun Valley, Idaho, May 1-5. 2016.


C.A. Gentry, G.I. Maldonado, K.S. Kim, “Development of Two-Step Analysis Procedure for the Advanced High Temperature Reactor,” PHYSOR 2016, Sun Valley, Idaho, May 1-5. 2016.


E.L. Jones, G.I. Maldonado, W.J. Marshall, C.M. Perfetti, B.T. Rearden, “Investigation of the Continuous-Energy Sensitivity Methods in Scale 6.2 using Tsunami-3D,” Proc. International Conference on Nuclear Criticality Safety (ICNC) 2015, Charlotte, North Carolina, September 13-17, 2015.


N.P. Luciano, K.E. Ottinger, P.E. Collins, C. Gentry, N. George, A.J. Pawel, K. Kenner, S. Hart, O. Chvala, G.I. Maldonado, F. Fejt, “The NESTLE 3D Nodal Core Simulator: Modern Reactor Models,” Proc. M&C+SNA+MC 2015, Nashville, TN, April 19-23, 2015.


N.M. George, J.J. Powers, G.I. Maldonado, A. Worrall, K.A. Terrani, “Development of a Full-Core Reactivity Equivalence for FeCrAl Enhanced Accident Tolerant Fuel in BWRs,” Proc. Advanced in Nuclear Fuel Management V, Hilton Head Island, March 29-April 1, 2015.


N.M. George, J.J. Powers, G.I. Maldonado, A. Worrall, K.A. Terrani, “Demonstration of a Full-Core Reactivity Equivalence for FeCrAl Enhanced Accident Tolerant Fuel in BWRs,” Proc. Advanced in Nuclear Fuel Management V, Hilton Head Island, March 29-April 1, 2015.


S.W.D. Hart, G.I. Maldonado, C. Celik, L.C. Leal, “Problem Dependent Doppler Broadening of Continuous Energy Cross Sections in the KENO Monte Carlo Computer Code,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, Sep. 28 – Oct. 3, 2014, on CD-ROM (2014)


J. Powers, N. George, A. Worrall, K. Terrani, G.I. Maldonado, “Reactor Physics Assessment of Alternate Cladding Materials,” Proc. of WRFPM 2014, Sendai, Japan, Sep. 14-17, 2014. Paper No. 100104.


C.J. Hurt, R.M. Wham, R.W. Hobbs, R. S. Owens, D. Chandler, J.D. Freels, G.I. Maldonado, “Plutonium-238 Production Target Design Studies,” Proc. of Institute of Nuclear Materials Management 55th Annual Meeting, Atlanta, GA, USA, 2014.

Peer-Reviewed Extended Abstracts
(Transactions of the American Nuclear Society)


T.A. Eckleberry, W.J. Marshall, E.L. Jones, and G.I. Maldonado, “Validation of KENO Thermal Moderator Doppler Broadening Method in SCALE 6.2b4 Using Continuous-Energy B-VII.1 Library,” Trans. Am. Nucl. Soc., 114, In Press, New Orleans, LA, Jun. 2016.


N.M. George, R.T. Sweet, G.I. Maldonado, B.D. Wirth, J.J. Powers, A. Worrall, “Fuel Performance Calculations for FeCrAl Cladding in BWRs,” Trans. Am. Nucl. Soc., 113, Washington, DC, Nov. 2015.


C. Gentry, G.I. Maldonado, O. Chvala, B. Petrovic, “Burnable Poison Reactivity Control for the Advanced High Temperature Reactor,” Trans. Am. Nucl. Soc., 113, Washington, DC, Nov. 2015.


P.E. Collins, N. Luciano, G.I. Maldonado, “Modernization and Expansion of Isotopic Depletion Capabilities within the NESTLE 3D Nodal Simulator,” Trans. Am. Nucl. Soc., 111, p. 1230-1233, Nov. 2014


N.M. George, J.J. Powers, G.I. Maldonado, K.A. Terrani, A. Worrall, “Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in Light Water Reactors,” Trans. Am. Nucl. Soc., 111, p. 1363-1366, Nov. 2014


E. Jones, W.J. Marshall, G.I. Maldonado, “Mixed Uranium-Plutonium Solution Validation of KENO V.a and KENO-VI in SCALE 6.1.2 and 6.2b3 Using Multigroup and Continuous-Energy ENDF/B-VII.0 Libraries,” Trans. Am. Nucl. Soc., 111, p. 857-860, Nov. 2014


K.R. Kenner, R. Montgomery, G.I. Maldonado, “Modeling an iPWR Startup Core Cycle with VERA,” Trans. Am. Nucl. Soc., 111, p. 1388-1390, Nov. 2014