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David Griesheimer

Assistant Professor
Stephen R. Tritch Nuclear Engineering Program Mechanical Engineering & Materials Science

about

PhD - Nuclear Engineering and Radiological Sciences, University of Michigan, 2000 - 2005

MSE - Nuclear Engineering and Radiological Sciences, University of Michigan, 2000 - 2002

BSE - Nuclear Engineering, University of Cincinnati, 1995 - 2000

BA - Mathematics, University of Cincinnati, 1995 - 2000

Kooreman, G., & Griesheimer, D.P. (2019). A fully analytic space-time depletion benchmark for fixed-source and eigenvalue calculations and its application to Monte Carlo simulation. ANNALS OF NUCLEAR ENERGY, 127, 99-110.Elsevier BV. doi: 10.1016/j.anucene.2018.11.048.

Gill, D.F., Griesheimer, D.P., & Aumiller, D.L. (2017). Numerical Methods in Coupled Monte Carlo and Thermal-Hydraulic Calculations. NUCLEAR SCIENCE AND ENGINEERING, 185(1), 194-205.Informa UK Limited. doi: 10.13182/NSE16-3.

Griesheimer, D.P., & Sandhu, V.S. (2017). Analysis of inconsistent source sampling in monte carlo weight-window variance reduction methods. Nuclear Engineering and Technology, 49(6), 1172-1180.Elsevier BV. doi: 10.1016/j.net.2017.07.017.

Griesheimer, D.P., Carpenter, D.C., & Stedry, M.H. (2017). Practical techniques for large-scale Monte Carlo reactor depletion calculatons. Progress in Nuclear Energy, 101, 409-423.Elsevier BV. doi: 10.1016/j.pnucene.2017.05.018.

Griesheimer, D.P., Pavlou, A.T., Thompson, J.T., Holmes, J.C., Zerkle, M.L., Caro, E., & Joo, H. (2017). In-line (α,n) source sampling methodology for monte carlo radiation transport simulations. Nuclear Engineering and Technology, 49(6), 1199-1210.Elsevier BV. doi: 10.1016/j.net.2017.08.004.

Griesheimer, D.P., Millman, D.L., & Willis, C.R. (2011). Analysis of distances between inclusions in finite binary stochastic materials. JOURNAL OF QUANTITATIVE SPECTROSCOPY & RADIATIVE TRANSFER, 112(4), 577-598.Elsevier BV. doi: 10.1016/j.jqsrt.2010.06.013.

Griesheimer, D.P., Martin, W.R., & Holloway, J.P. (2006). Convergence properties of Monte Carlo functional expansion tallies. JOURNAL OF COMPUTATIONAL PHYSICS, 211(1), 129-153.Elsevier BV. doi: 10.1016/j.jcp.2005.05.023.

Griesheimer, D.P., Martin, W.R., & Holloway, J.P. (2005). Estimation of flux distributions with Monte Carlo functional expansion tallies. RADIATION PROTECTION DOSIMETRY, 115(1-4), 428-432.Oxford University Press (OUP). doi: 10.1093/rpd/nci265.

Burke, P.E., Remley, K.E., & Griesheimer, D.P. (2021). GPU ACCELERATION OF DOPPLER BROADENING FOR NEUTRON TRANSPORT CALCULATIONS1. In EPJ Web of Conferences, 247, (p. 04017).EDP Sciences. doi: 10.1051/epjconf/202124704017.

Kooreman, G., & Griesheimer, D.P. (2021). PREDICTOR-CORRECTOR QUASI-STATIC METHOD FOR TIGHTLY-COUPLED REACTOR MULTIPHYSICS TRANSIENT CALCULATIONS. In EPJ Web of Conferences, 247, (p. 07011).EDP Sciences. doi: 10.1051/epjconf/202124707011.

Remley, K.E., & Griesheimer, D.P. (2021). A SEMI-ANALYTIC EIGENVALUE EXTENSION TO THE DOPPLER SLAB ANALYTIC BENCHMARK1. In EPJ Web of Conferences, 247, (p. 04018).EDP Sciences. doi: 10.1051/epjconf/202124704018.

Griesheimer, D.P., & Gibson, N.A. (2019). Simplified method for estimating the effective delayed neutron fraction with Monte Carlo correlated sampling. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, (pp. 886-895).

Remley, K.E., & Griesheimer, D.P. (2019). A fully analytic coupled thermal-neutronics benchmark and its application to Monte Carlo simulation. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, (pp. 1744-1760).

Remley, K.E., Griesheimer, D.P., Hogan, K.J., & Buchanan, J.R. (2019). Investigations into coupling the MC21 Monte Carlo transport code to the CFX computational fluid dynamics code. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, (pp. 1400-1410).

Thompson, J.T., Griesheimer, D.P., & Caro, E. (2019). Pre-collapsed fluorescence methodology for Monte Carlo radiation transport simulations. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, (pp. 507-513).

Kooreman, G., & Griesheimer, D.P. (2018). A fully analytic space-time depletion benchmark and its applications to Monte Carlo simulation. In International Conference on Physics of Reactors, PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems, Part F168384-1, (pp. 147-165).

Kooreman, G., & Griesheimer, D.P. (2018). An eigenvalue extension to the candlestick analytic space-time depletion benchmark and its application to Monte Carlo simulation. In AISTech - Iron and Steel Technology Conference Proceedings, 2018-May, (pp. 443-446).

Kooreman, G., & Griesheimer, D.P. (2018). An eigenvalue extension to the candlestick analytic space-time depletion benchmark and its application to Monte Carlo simulation. In Transactions of the American Nuclear Society, 118, (pp. 443-446).

Griesheimer, D.P., Aumiller, D.L., & Gill, D.F. (2017). Proposed semi-analytic benchmark for coupled neutronics/thermal-hydraulics feedback in multiphysics simulations. In Transactions of the American Nuclear Society, 116, (pp. 1285-1289).

Rathbun, M.A., & Griesheimer, D.P. (2017). Effect of delayed energy release on power normalization in reactor depletion calculations. In Transactions of the American Nuclear Society, 116, (pp. 1144-1148).

Griesheimer, D.P. (2016). In-line method for calculating peak neutron absorption by fission products following a change in reactor power. In Transactions of the American Nuclear Society, 115, (pp. 578-582).

Griesheimer, D.P., & Nease, B.R. (2016). Improved weight window variance reduction for coupled radiation Monte Carlo transport calculations. In Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, 5, (pp. 3306-3315).

Griesheimer, D.P., Carpenter, D.C., & Stedry, M.H. (2016). Techniques for practical Monte Carlo reactor depletion calculatons. In Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, 1, (pp. 477-493).

Griesheimer, D.P., Marin, S.C., Romano, P.K., & Stedry, M.H. (2016). Integrated decay source capability for large-scale Monte Carlo radiation transport calculations. In Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, 3, (pp. 1532-1543).

Caro, E., Romano, P.K., Marin, S.C., & Griesheimer, D.P. (2015). Relativistic kinematics for photoneutron production in Monte Carlo transport calculations. In Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, 1, (pp. 134-147).

Gill, D.F., Griesheimer, D.P., & Aumiller, D.L. (2015). Numerical methods in coupled Monte Carlo and thermal-hydraulic calculations. In Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, 3, (pp. 1926-1942).

Griesheimer, D.P., & Goter, T.P. (2015). Estimating the effective neutron generation time with Monte Carlo correlated sampling. In Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, 1, (pp. 18-34).

Griesheimer, D.P., Gill, D.F., Nease, B.R., Sutton, T.M., Stedry, M.H., Dobreff, P.S., Carpenter, D.C., Trumbull, T.H., Caro, E., Joo, H., & Millman, D.L. (2015). MC21 v.6.0-A continuous-energy Monte Carlo particle transport code with integrated reactor feedback capabilities. In ANNALS OF NUCLEAR ENERGY, 82, (pp. 29-40).Elsevier BV. doi: 10.1016/j.anucene.2014.08.020.

Griesheimer, D.P., Nease, B.R., Dobreff, P.S., Romano, P.K., & Gill, D.F. (2015). Strategies and algorithms for hybrid shared-memory/message-passing parallelism in Monte Carlo radiation transport codes. In Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, 2, (pp. 1449-1471).

Willis, C.R., Griesheimer, D.P., & Schneider, E. (2015). Accuracy of the chord length sampling method near boundaries of 1-D finite stochastic materials. In Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, 2, (pp. 1023-1039).

Gill, D.F., Aumiller, D.L., & Griesheimer, D.P. (2014). Monte Carlo and thermal-hydraulic coupling via PVMEXEC. In Proceedings of the International Conference on Physics of Reactors, PHYSOR 2014.

Griesheimer, D.P. (2014). Scalability of Monte Carlo cross-section lookup algorithms for large models. In Transactions of the American Nuclear Society, 111, (pp. 703-707).

Griesheimer, D.P., & Gouw, R.R. (2014). Using composite nuclides to reduce cross section lookups in Monte Carlo transport simulations. In Transactions of the American Nuclear Society, 111, (pp. 708-712).

Spychala, S.J., & Griesheimer, D.P. (2014). Effects of stochastic noise on a three-dimensional Monte Carlo depletion analysis of the H.B. Robinson reactor. In Proceedings of the International Conference on Physics of Reactors, PHYSOR 2014.

Densmore, J.D., Gill, D.F., & Griesheimer, D.P. (2013). Stability analysis of burnup calculations. In Transactions of the American Nuclear Society, 109(PART 1), (pp. 695-698).

Gill, D.F., Nease, B.R., & Griesheimer, D.P. (2013). Movable geometry and eigenvalue search capability in the MC21 Monte Carlo code. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013, 2, (pp. 1429-1440).

Griesheimer, D.P., & Stedry, M.H. (2013). A generalized framework for in-line energy deposition during steady-state Monte Carlo radiation transport. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013, 1, (pp. 623-637).

Hackemack, M.W., Ragusa, J.C., Griesheimer, D.P., & Pounders, J.M. (2013). A Monte Carlo implementation of the predictor-corrector Quasi-Static method. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013, 3, (pp. 1953-1964).

Hanna, B.R., Gill, D.F., & Griesheimer, D.P. (2013). REACTIVITY EFFECTS OF SPATIAL HOMOGENIZATION OF THERMAL FEEDBACK REGIONS IN MONTE CARLO REACTOR CALCULATIONS. In NUCLEAR TECHNOLOGY, 183(3), (pp. 367-378).Informa UK Limited. doi: 10.13182/NT13-A19425.

Toth, B.E., Martin, W.R., & Griesheimer, D.P. (2013). Normality of Monte Carlo criticality eigenfunction decomposition coefficients. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013, 4, (pp. 2852-2864).

Willis, C.R., Schneider, E., & Griesheimer, D.P. (2013). Characterization of types of inclusion edge effects in finite stochastic materials. In Transactions of the American Nuclear Society, 109(PART 1), (pp. 767-770).

Hanna, B.R., Gill, D.F., & Griesheimer, D.P. (2012). Spatial homogenization of thermal feedback regions in Monte Carlo reactor calculations. In International Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics, 2, (pp. 1007-1022).

Millman, D.L., Griesheimer, D.P., Nease, B.R., & Snoeyink, J. (2012). Robust volume calculations for Constructive Solid Geometry (CSG) components in Monte Carlo transport calculations. In International Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics, 1, (pp. 826-841).

Griesheimer, D.P. (2010). In-line xenon convergence algorithm for Monte Carlo reactor calculations. In International Conference on the Physics of Reactors 2010, PHYSOR 2010, 1, (pp. 660-679).

Griesheimer, D.P., & Millman, D.L. (2009). Analysis of distances between inclusions in finite one-dimensional binary stochastic materials. In American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009, 2, (pp. 1150-1178).

Wilson, S.C., & Griesheimer, D.P. (2009). Rejection sampling from a spherical harmonics angular flux functional expansion for a discrete ordinates to Monte Carlo splice. In American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009, 2, (pp. 1311-1333).

Griesheimer, D.P., Gill, D.F., Lane, J.W., & Aumiller, D.L. (2008). An integrated thermal hydraulic feedback method for Monte Carlo reactor calculations. In International Conference on the Physics of Reactors 2008, PHYSOR 08, 1, (pp. 700-707).

Griesheimer, D.P., & Toth, B.E. (2007). A novel source convergence acceleration scheme for Monte Carlo criticality calculations, part I: Theory. In Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + SNA 2007.

Sutton, T.M., Donovan, T.J., Trumbull, T.H., Dobreff, P.S., Caro, E., Griesheimer, D.P., Tyburski, L.J., Carpenter, D.C., & Joo, H. (2007). The MC21 Monte Carlo transport code. In Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + SNA 2007.

Toth, B.E., & Griesheimer, D.P. (2007). A novel source convergence acceleration scheme for Monte Carlo criticality calculations, part II: Implementation & results. In Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + SNA 2007.

Griesheimer, D.P., Cheatham, J., Holloway, J.P., & Martin, W.R. (2005). Improving Monte Carlo source convergence with the functional expansion technique. In Transactions of the American Nuclear Society, 93, (pp. 461-463).

Griesheimer, D.P., Martin, W.R., & Holloway, J.P. (2005). A functional expansion method for Monte Carlo eigenvalue calculations. In Monte Carlo 2005 Topical Meeting, (pp. 273-290).

Brown, F.B., Griesheimer, D., & Martin, W.R. (2004). Continuously varying material properties and tallies for Monte Carlo calculations. In Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, (pp. 183-190).

Griesheimer, D.P., & Martin, W.R. (2004). Two dimensional functional expansion tallies for Monte Carlo simulations. In Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, (pp. 153-160).

Griesheimer, D.P., & Martin, W.R. (2003). Estimating the Global Scalar Flux Distribution with Orthogonal Function Expansions. In Transactions of the American Nuclear Society, 89, (p. 462).

Griesheimer, D.P., & Martin, W.R. (2003). Monte-Carlo Based Angular Flux Response Functions. In Transactions of the American Nuclear Society, 89, (p. 370).

Griesheimer, D.P. (2001). Isotopic transmutation and destruction rates in various neutron energy spectra. In Transactions of the American Nuclear Society, 85, (p. 525).