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Aaron Epiney

Engineer

Research Areas:

Biography:

Dr. Epiney obtained his Master of Science MSc degree in Physics in 2005 from the Ecole Polytechnique Federale de Lausanne (EPFL) in Lausanne, Switzerland. Following his Master degree, Dr. Epiney worked at the Paul Scherrer Institute (PSI) in collaboration with the EPFL in Switzerland and CEA in France on his Ph.D. thesis in Physics which he successfully defended in 2010.

Dr. Epiney’s research interests include nuclear thermal-hydraulics, neutronincs as well as economics; especially thermal-hydraulic safety analysis, in-core and system design and modelling, multi-physics simulations using coupled neutronics and thermal-hydraulics, economical performance analysis of power plants, code development as well as uncertainty quantification and propagation.

After his PhD, Dr. Epiney worked at the Idaho National Laboratory (INL) in the Reactor Physics Analysis and Design department where he helped develop the reactor analysis code package PHISICS and its coupling to RELAP5-3D, a thermal-hydraulic system code, making PHISICS a comprehensive reactor physics package for reactor design and safety analysis.

From 2013 to 2015, Dr. Epiney left the INL to go back to Switzerland working once more at PSI. During this time, he was the lead analyst for the thermal hydraulic safety calculations for one for the Swiss boiling water reactors.

Dr. Epiney currently works in the Nuclear Engineering Methods Development department at INL where his research includes a modeling and simulation effort called HYBRID which goal is to assess the economic viability of hybrid nuclear systems in a market that contains renewable energy sources like wind or solar. Furthermore, Dr. Epiney is involved in core and system analysis for LWRs as well as HTRs using the PHISICS/RELAP5-3D code package he helped develop.

Education:

​Ph.D. Physics - Ecole Polytechnique Federale de Lausanne, Switzerland

M.S., Physics -  Ecole Polytechnique Federale de Lausanne, Switzerland

Presentations:

​S. Rahman, D. R. Karanki, A. Epiney, D. Wicaksono, O. Zerkak, V. Dang, “Deterministic Sampling for Propagating Epistemic and Aleatory Uncertainty in DET Analysis of a Nuclear Power Plant”, Reliability Engineering and System Safety, 2018, 175: p. 62-78.

 

T. Baker, A. Epiney, C. Rabiti, E. Shittu, “Optimizing Subsystem Capacity for a Nuclear Renewable Hybrid Energy System”, Applied Energy, 2018, 212: p. 498-508.

 

A. Epiney, Carlo Parisi, Andrea Alfonsi, Hongbin Zhang, Ronaldo Szilard, “RISMC Industry Application #1 (ECCS/LOCA): Core characterization automation: Reference PWR designs for IA#1”, Proceedings American Nuclear Society 2017 Summer Meeting, San Francisco, CA, USA, June 11-15, 2017.

 

A. Epiney, A. Alfonsi, C. Rabiti, J. Chen, “Economic Assessment of Nuclear Hybrid Energy Systems: Optimization using RAVEN”, Proceedings American Nuclear Society 2017 Summer Meeting, San Francisco, CA, USA, June 11-15, 2017.

 

A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi, “Towards a Consolidated Approach for the Assessment of Evaluation Models of Nuclear Power Reactors”, Nuclear Technology, NURETH-16 Special issue, 2016. 196: p. 223-237.

 

C. Cozzo, A. Epiney, S. Canepa, H. Ferroukhi, O. Zerkak, G. Khvostov, V. Brankov, A. Gorzel, “Full Core LOCA Analysis for BWR/6 – Methodology and First Results”, Top Fuel conference, Boise ID, USA, September 11-16, 2016.

 

A. Epiney, C. Parisi, H. Zhang, R. Szilard, “RISMC Industry Application #1 (ECCS/LOCA) - Core characterization automation: Lattice Codes interface for PHISICS/RELAP5-3D”, Proceedings American Nuclear Society 2016 Summer Meeting, New Orleans, USA, June 12-16, 2016.

 

A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi, “Towards a Consolidated Approach for the Validation of Plant System Codes and Models: Case Study for a BWR Fast Depressurisation Event”, NURETH-16 conference, Chicago, USA, August 30-September 4, 2015.

 

S. Rahman, D. R. Karanki, A. Epiney, O. Zerkak, V. N. Dang, “Ranking of Uncertain Parameters for Dynamic Event Tree Analysis: A Case Study Based on a Station Blackout Scenario”, NURETH-16 conference, Chicago, USA, August 30-September 4, 2015.

 

A. Epiney, O. Zerkak, A. Pautz, “Uncertainty- and Sensitivity Analysis of COBRA-TF for the Simulation of Selected OECD/NRC BFBT Void Experiments”, NUTHOS10, Okinawa, Japan, December 14-18, 2014.

 

G. Strydom, A. Epiney, A. Alfonsi, C. Rabiti, “Comparison of the PHISICS/RELAP5-3D Ring and Block Model Results for Phase I of the OECD/NEA MHTGR-350 Benchmark”, Nuclear Technology, 2016. 193: p. 15-35.

 

C. Rabiti, A. Alfonsi, A. Epiney, “New Simulation Schemes and Capabilities for the PHISICS/RELAP5-3D Coupled Suite”, Nuclear Science and Engineering, 2016. 182: p. 104-118.

 

A. Mabe, A. Alfonsi, C. Rabiti, A. Epiney, M. Lineberry, “Development of Fuel Shuffling Module for PHISICS”, Proceedings American Nuclear Society 2013 Annual Meeting, Atlanta, USA, June 16-20, 2013.

 

F. Lodi, C. Rabiti, A. Alfonsi, A. Epiney, M. Sumini, “Hot Zero and Full Power Validation of PHISICS RELAP-5 Coupling”, Proceedings American Nuclear Society 2013 Annual Meeting, Atlanta, USA, June 16-20, 2013.

 

A. Epiney, G. Strydom, A. Alfonsi, C. Rabiti, “New Multi-group Transport Neutronics (PHISICS) Capabilities for RELAP5-3D and its Application to Phase I of the OECD/NEA MHTGR-350 MW Benchmark”, HTR 2012, Tokyo, Japan, October 28 - November 1, 2012.

 

A. Epiney, C. Rabiti, A. Alfonsi, Y. Wang, J. Cogliati, G. Strydom, “PHISICS multi-group transport neutronic capabilities for RELAP5”, ICAPP’12, Chicago, USA, June 24-28, 2012.

 

G. Strydom, A. Epiney, “RELAP5-3D Results for Phase I (Exercise 2) of the OECD/NEA MHTGR-350 MW Benchmark”, ICAPP’12, Chicago, USA, June 24-28, 2012.

 

A. Alfonsi, C. Rabiti, A. Epiney, Y. Wang, J. Cogliati, “PHISICS Toolkit: Multi-Reactor Transmutation analysis utility - MRTAU”, PHYSOR 2012, Knoxville, USA, April 15-20, 2012.

 

C. Rabiti, Y. Wang, G. Palmiotti, H. Hiruta, J. Cogliati, A. Alfonsi, A. Epiney, T. Grimmet, “PHISICS: New Features and Advancements”, Proceedings American Nuclear Society 2011 Annual Winter Meeting, Washington, D. C., USA, October 30-November 3, 2011.

 

A. Epiney, N. Alpy, K. Mikityuk, R. Chawla, “A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions”, Nuclear Engineering and Design, 2012. 242: p. 267-284

A. Epiney, “Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast reactor”, Thesis “École polytechnique fédérale de Lausanne” EPFL, n° 4792 (2010).

 

G. Girardin, A. Epiney, O. P. Joneja, “Modelling of a double fission chamber using MCNPX for power calibration at the zero-power teaching reactor CROCUS”, M&C2010, Tokyo, Japan, October 17-21, 2010.

 

A. Epiney, K. Mikityuk, R. Chawla, “TRACE Qualification via Analysis of the EIR Gas-Loop Experiments with Smooth Rods”, Annals of Nuclear Energy, 2010. 37(6): p. 875-887.

 

A. Epiney, K. Mikityuk, R. Chawla, “Heavy-Gas Injection in the Generation IV Gas-cooled Fast Reactor for Improved Decay Heat Removal under Depressurized Conditions”, Nuclear Engineering and Design, 2010. 240(10): p. 3115-3125.

 

G. Girardin, A. Epiney, K. Mikityuk, R. Chawla, “Neutronic Analysis of Water-Steam Injection Accidents for Generation IV Gas-Cooled Fast Reactors”, PHYSOR 2010, Pittsburgh, USA, May 9-14, 2010 .

 

A. Epiney, N. Alpy, D. Haubensack, JY. Malo, K. Mikityuk, R. Chawla, “Preliminary Design of a Brayton Cycle as a Standalone Decay Heat Removal System of the Gas Fast Reactor”, NURETH-13 conference, Kanazawa City, Japan, September 27-October 2, 2009.

 

A. Epiney, K. Mikityuk, R. Chawla, “Heavy Gas Injection in the Gen-IV Gas Cooled Fast Reactor to Improve Decay Heat Removal Under Depressurised Conditions”, NURETH-13 conference, Kanazawa City, Japan, September 27-October 2, 2009.

 

A. Epiney, K. Mikityuk, R. Chawla, “Gas-Cooled Fast Reactor: Studies on Safety Enhancement”, IYCE09, Budapest, Hungary, June 4-6, 2009.

 

S. Pelloni, K. Mikityuk, A. Epiney, “A New Cross-Section Generation Model in the FAST Code System and its Application to the Gen-IV Gas-Cooled Fast Reactor”, M&C2009, Saratoga Springs, USA, May 3-7, 2009.

 

A. Epiney, P. Dumaz, P. Coddington, K. Mikityuk, R. Chawla, “Comparative transient analysis of the 2400MWth GFR with the TRACE and CATHARE codes”, PHYSOR 2008, Interlaken, Switzerland, September 14-19, 2008.

 

A. Epiney, P. Coddington, K. Mikityuk, R. Chawla, “New Analysis of the EIR GFR Thermal-hydraulic Experiments”, PHYSOR 2008, Interlaken, Switzerland, September 14-19, 2008.

 

P. Dumaz, A. Epiney, N. Alpy, P. Broxtermann, J. Malo, A. Tosello, “Studies of Unprotected Transients and Alternative Decay Heat Removal System for the Gas -cooled Fast Reactor (GFR)”, ICAPP'08, Anaheim, USA, June 8-12, 2008.

 

A. Epiney, S. Pelloni, P. Coddington, R. Chawla, “Comparative analysis for the initial cycle of two Generation IV GFRs (600MW) operating with innovative CERCER carbide fuel”, IEMPT ’06, Nimes, France, September 25-29, 2006.


RELEVANT REPORTS
C. Rabiti, A. Epiney, P. Talbot, J. S. Kim, S. Bragg-Sitton, A. Alfonsi, A. Yigitoglu, S. Greenwood, S. M. Cetiner, F. Ganda, G. Maronati, “Status Report on Modelling and Simulation Capabilities for Nuclear-Renewable Hybrid Energy Systems”, Idaho National Laboratory, September 2017, INL/EXT-17-43441.

 

H. Zhang, R. Szilard, A. Epiney, C. Parisi, R. Vaghetto, A. Vanni, K. Neptune, “Industry Application ECCS / LOCA Integrated Cladding/Emergency Core Cooling System Performance: Demonstration of LOTUS-Baseline Coupled Analysis of the South Texas Plant Model”, Idaho National Laboratory, June 2017, INL/EXT-17-42461.

 

T. McJunkin, A. Epiney, C. Rabiti, “Report on Integration of Existing Grid Models for N-R HES Interaction Focused on Balancing Authorities for Sub-hour Penalties and Opportunities”, Idaho National Laboratory, June 2017, INL/EXT-42534.

 

A. Epiney, C. Rabiti, A. Alfonsi, P. Talbot, F. Ganda, “Report on the Economic Optimization of a Demonstration Case for a Static N-R HES Configuration using RAVEN”, Idaho National Laboratory, April 2017, INL/EXT-17-41915.

 

A. Epiney, H. Zhang, C. Parisi, R. Szilard, “Risk-Informed Safety Margin Characterization – Industry Application 1: A RELAP5-3D/Core/Fuel/Clad Coupling Application”, IRUG meeting, Idaho Falls, ID, USA, October 2016, INL/CON-16-40145.

 

A. Epiney, R. Kinoshita, J. Kim, C. Rabiti, M. Greenwood, “Software Development Infrastructure for the HYBRID Modeling and Simulation Project”, Idaho National Laboratory, September 2016, INL/EXT-16-40004.

 

A. Epiney, J. Chen, C. Rabiti, “Status on the Development of a Modeling and Simulation Framework for the Economic Assessment of Nuclear Hybrid Energy Systems (FY 16)”, Idaho National Laboratory, September 2016, INL/EXT-16-39832.

 

R. Szilard, H. Zhang, A. Epiney, C. Parisi, P. Talbot, “Loss of Coolant Accident / Emergency Core Coolant System Evolution of Risk-Informed Margins Management Strategies for a Representative Pressurized Water Reactor”, Idaho National Laboratory, September 2016, INL/EXT-16-39805.

 

A. Epiney, “PSI Reference Model Data Report – KKL RTACE Model 2014: Steam Lines”, Paul Scherrer Institut, July 2015, TM-41-14-16.

 

A. Epiney, “PSI Reference Model Data Report – KKL TRACE Model 2014: Feedwater Lines”, Paul Scherrer Institut, December 2014, TM-41-14-15.

 

A. Alfonsi, C. Rabiti, A. Epiney, “Capabilities of PHISICS/RELAP5-3D”, IRUG meeting, Idaho Falls, ID, USA, September 2014.

 

A. Epiney, O. Zerkak, “FLICA input models for PWR MSLB analysis”, NURESAFE deliverable, May 2014, NURESAFE-D12.22.

 

A. Epiney, C. Rabiti, A. Alfonsi, G. Strydom, “RELAP5-3D/PHISICS coupling advancements”, IRUG meeting, Sun Valley, ID, USA, October 2012, INL/CON-12-27552.

 

C. Rabiti, Y. Wang, G. Palmiotti, A. Epiney, A. Alfonsi, H. Hiruta, J. Cogliati, T. Grimmett, “Advanced Neutronics: PHISICS project”, IRUG meeting, Salt Lake City, UT, USA, July 2011, INL/MIS-11-23016.

 

A. Epiney, C. Rabiti, Y. Wang, J. Cogliati, T. Grimmett, P. Palmiotti, “INSTANT/PHISICS – RELAP5-3D coupling”, IRUG meeting, Salt Lake City, UT, USA, July 2011, INL/MIS-11-22767.

 

A. Epiney, “Transient analysis for the 2400MWth GCFR: Comparison between the ‘0604’ and ‘F’ core designs and the TRACE and CATHARE codes”, Paul Scherrer Institut, October 2008, TM-41-08-13/2.

 

A. Epiney, “GCFR Loop experiments at EIS with different gases”, Paul Scherrer Institut, August 2006, TM-41-07-09.

Awards:

​INL instant recognition award for exceptional contribution to the U.S. Department of Energy level 2 performance milestone report on simulation and optimisation of dynamic NR HES models, 2017

INL recognition award for the successful delivery of the U.S. Department of Energy level 2 performance milestone rapport on the LWR LOCA methodology development (LOTUS), 2016

INL instant recognition award for exceptional effort in the creation of the HELL core design, 2016

PSI instant recognition award for exceptional work on BWR TRACE modelling, 2014

Outstanding Presentation Award for Young Researcher, HTR (International Topical Meeting on High Temperature Reactor Technology) in Tokyo, Japan, October 28 – November 1, 2012

INL patent award for the PHISICS copyright and licensing, 2012

INL instant recognition award for exceptional work on PHISICS, 2011

Best paper and presentation prize at the ENEN (European Nuclear Education Network) PhD Event 2009 in Budapest, Hungary, June 5, 2009

Research Interests:

​Nuclear thermal-hydraulics, Neutronincs, Economics, Thermal-hydraulic safety analysis, In-core and system, design and modelling, Multi-physics simulations

Version: 6.0
Created at 3/22/2018 8:01 AM by Phyllis L. King
Last modified at 5/23/2018 12:51 PM by Phyllis L. King