Buschman, F.X., & Aumiller, D.L. (2017). Use of fundamental condensation heat transfer experiments for the development of a sub-grid liquid jet condensation model. Nuclear Engineering and Design, 312, 147-160.Elsevier. doi: 10.1016/j.nucengdes.2016.06.040.
Aumiller, D., Buschman, F., Tomlinson, E., & Gill, D. (2016). Development of an Integrated Code System Using R5EXEC and RELAP5-3D. NUCLEAR TECHNOLOGY, 193(1), 183-199.Taylor & Francis. doi: 10.13182/NT15-5.
Mesina, G.L., Aumiller, D.L., & Busehman, F.X. (2016). Extremely Accurate Sequential Verification of RELAP5-3D. NUCLEAR SCIENCE AND ENGINEERING, 182(1), 1-12.Taylor & Francis. doi: 10.13182/nse14-151.
Mesina, G.L., Aumiller, D.L., Buschman, F.X., & Kyle, M.R. (2016). Modeling Moving Systems with RELAP5-3D. NUCLEAR SCIENCE AND ENGINEERING, 182(1), 83-95.Taylor & Francis. doi: 10.13182/NSE15-3.
Frepoli, C., Yurko, J.P., Buschman, F., & Aumiller, D. (2016). Results from the assessment of COBRA-IE multidimensional flow capability with selected canonical problems. In International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016, (pp. 41-52).
Aumiller, D.L., Swartele, G.W., Meholic, M.J., Lloyd, L.J., & Buschman, F.X. (2015). COBRA-IE: A new Sub-Channel analysis code. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 5, (pp. 3832-3845).
Buschman, F.X., & Aumiller, D.L. (2015). Development of A Sub-Grid liquid jet condensation model. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 5, (pp. 3846-3859).
Buschman, F.X., Aumiller, D.L., Hochreiter, L.E., Cheung, F.B., Johnson, D.K., Meholic, M.J., & Skilone, D.J. (2015). Fundamental experiments of condensation heat transfer on water jets in the presence of noncondensable gas. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 10, (pp. 8374-8385).
Frepoli, C., Fricano, J.W., Buschman, F., & Aumiiler, D. (2015). Simulation of faraday waves with the RELAP5-3D thermal-hydraulic code. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 4, (pp. 3351-3364).
Frepoli, C., Fricano, J.W., Yurko, J.P., Buschman, F., & Aumilier, D. (2015). On the definition of a minimum set of requirements to assess the adequacy of the RELAP5-3D multidimensional flow capability with selected canonical problems. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 4, (pp. 3336-3350).
Frepoli, C., Yurko, J.P., Fricano, J.W., Buschman, F., & Aumiller, D. (2015). On the level of approximation of the multi-dimensional potential flow solution in complex geometries with thermal-hydraulic system codes. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 4, (pp. 3365-3377).
Mesina, G.L., Aumiller, D.L., & Buschman, F.X. (2014). Automated, Highly Accurate Verification of RELAP5-3D. In Volume 2B: Thermal Hydraulics, 2B, (p. v02bt09a054).ASME International. doi: 10.1115/icone22-31153.