Math and Comp / Poster Exhibit Hall -- ANS / Meetings / Mathematics & Computation (M&C) 2021

About ANS
- ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
About Nuclear
- Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Communities
- Division Spotlight
  Isotopes & Radiation
  Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meetings
- Meeting Spotlight
  2023 ANS Annual Meeting
  June 11–14, 2023
  Indianapolis, IN|Marriott Indianapolis Downtown
Standards
- Standards Program
  The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Publications
- Latest Magazine Issues
  Jun 2023
  Jan 2023
  Latest Journal Issues
  Nuclear Science and Engineering
  June 2023
  Nuclear Technology
  June 2023
  Fusion Science and Technology
  July 2023
- Latest News
  The Civil Nuclear Credit Program: An overview
  Officially established on November 15, 2021, with the signing of the $1.2 trillion Infrastructure Investment and Jobs Act—aka the Bipartisan Infrastructure Law, or BIL—the Department of Energy’s Civil Nuclear Credit Program was designed to give owners/operators of commercial U.S. reactors the opportunity to apply for certification and competitively bid on credits to help support the continued operation of economically troubled units. Finally, the federal government, and not just certain farsighted state governments, would recognize nuclear energy for its important grid reliability and decarbonization attributes.
Search

Poster Lightning Talks: Transport Methods, Parallel Algorithms, Applications, and Validation

Go to session page

Poster Title	Authors
Consistent Temperature and Intensity Calculations From Deterministic Phonon Transport	Nicholas H. Whitman (Oregon State Univ.), Todd S. Palmer (Oregon State Univ.), P. Alex Greaney (Univ. of California - Riverside), Dmitriy Y. Anistratov (NC State Univ.)
A Hybrid Deterministic-Stochastic Method for the Calculation of Dose Rate in Reactor Dismantling Operations	Ettore Guadagni (CEA), Yannick Pénéliau (CEA), Jean Michel Létang (Univ. de Lyon), François-Xavier Hugot (CEA), Cindy Le Loirec (CEA)
Radiation Shielding Calculations at VTT Centre for Nuclear Safety Using the Serpent 2 Monte Carlo Code	Jaakko Leppänen (VTT Technical Research Centre of Finland), Mika Jokipii (VTT Technical Research Centre of Finland)
Neutronics Simulation of the Molten Salt Reactor Experiment With SCALE/Shift and Serpent/PARCS	Jin Li (Univ. of Michigan), Shai Kinast (Univ. of Michigan), Volkan Seker (Univ. of Michigan), Jipu Wang (Univ. of Michigan), Andrew Ward (Univ. of Michigan), Brendan Kochunas (Univ. of Michigan), Thomas Downar (Univ. of Michigan), Ugur Mertyurek (ORNL)
A Novel Monte Carlo Leakage Correction for Serpent 2	Ville Valtavirta (VTT Technical Research Centre of Finland), Jaakko Leppänen (VTT Technical Research Centre of Finland)
Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics	Diego Ferraro (Karlsruhe Institute for Technology), Manuel García (Karlsruhe Institute for Technology), Ville Valtavirta (VTT Technical Research Centre of Finland), Uwe Imke (Karlsruhe Institute for Technology), Riku Tuominen (VTT Technical Research Centre of Finland), Jaakko Leppänen (VTT Technical Research Centre of Finland Ltd), Victor Sanchez-Espinoza (Karlsruhe Institute for Technology)
Multigroup Cross-Section Generation for Versatile Test Reactor Experiments Analysis	Alisha Kasam-Griffith (ANL), Adam Nelson (ANL), Florent Heidet (ANL)
Validation of RAPID's Algorithm for Control Rods Movement Using the JSI TRIGA Reactor	Valerio Mascolino (Virginia Tech), Alireza Haghighat (Virginia Tech), Anže Pungerčič (Jožef Stefan Institute), Luka Snoj (Jozef Stefan Institute)
Modelling of the OPEN100 Reactor with the Serpent-2 Code	Anže Mihelčič (Jozef Stefan Institute), Anze Pungercic (Jozef Stefan Institute), Dusan Calic (Jozef Stefan Institute), Luka Snoj (Jozef Stefan Institute)
Improvements on Power Calibration and Core Monitoring at the Penn State Breazeale Reactor With MCNP	Gokhan Corak (Penn State Univ.), William J. Walters (Penn State Univ.)
An Adaptation of the Coarse Mesh Transport (COMET) Method for Improved Parallelism Targeting GPU Architectures	Paul Burke (Georgia Institute of Technology), Farzad Rahnema (Georgia Institute of Technology), Dingkang Zhang (Georgia Institute of Technology)
Monte Carlo Scalability on Extreme Memory Computing Nodes	David P. Griesheimer (Naval Nuclear Laboratory), Peter S. Dobreff (Naval Nuclear Laboratory), Roberto Gomez (Pittsburgh Supercomputing Center)
New Route in TRIPOLI-4® for Radiation Dosimetry Calculations Using ICRP 110 Voxel Phantoms	Yi-Kang Lee (CEA), François-Xavier Hugot (CEA), Yue Jin (CEA)
3-D Monte Carlo vs SN Deterministic Radiation Transport Methods Supporting an Optimized Neutron Imaging Source at the Utah TRIGA Reactor	Michael J. Hartos (Univ. of Utah), Meng-Jen Wang (Univ. of Utah), Glenn E. Sjoden (Univ. of Utah)

Poster Lightning Talks: Computational Tools for Multiphysics Problems

Go to session page

Poster Title	Authors
Recent Advances of the FENNECS NEutroniCS Code for Safety Assessment of (v)SMR, Generation IV and Other Innovative Concepts	A. Seubert (Gesellschaft für Anlagen- und Reaktorsicherheit), J. Bousquet (Gesellschaft für Anlagen- und Reaktorsicherheit), R. Henry (Gesellschaft für Anlagen- und Reaktorsicherheit)
Recent Advances of the FENNECS NEutroniCS Code for Safety Assessment of (v)SMR, Generation IV and Other Innovative Concepts	A. Seubert (Gesellschaft für Anlagen- und Reaktorsicherheit), J. Bousquet (Gesellschaft für Anlagen- und Reaktorsicherheit), R. Henry (Gesellschaft für Anlagen- und Reaktorsicherheit)
Development of an OpenFOAM interface for ENRICO	Lance Bullerwell (NC State Univ.), Patrick Shriwise (ANL), Paul Romano (ANL), Ron Rahaman (ANL), Jason Hou (NC State Univ.)
Modeling of Koeberg Power Plant: Generation of Nominal and Perturbed Nuclear Data With Polaris for PARCS Simulations	Pascal Rouxelin (NC State Univ.), Agustin Abarca (NC State Univ.), Maria Avramova (NC State Univ.), Margaret Mkhosi (Centre for Nuclear Safety and Security), Ian Korir (Centre for Nuclear Safety and Security)
Analysis of Rod Ejection Accident in Cycle 23 of Koeberg NPP with PARCS and CTF/PARCS	A. Abarca (NC State Univ.), C. Takasugi (NC State Univ.), R. Tshipuke (NC State Univ.), P. Rouxelin (NC State Univ.), M. Avramova (NC State Univ.), M. Mkhosi (Centre for Nuclear Safety and Security), I. Korir (Centre for Nuclear Safety and Security)
Implementation of Dynamic Monte Carlo Simulation in iMC and Multi-Physics Analysis on Advanced Fuel Element	HyeonTae Kim (KAIST), Yonghee Kim (KAIST)
On the Creation of the New ENDF/B-VIII.0 Covariance Library for SCALE Applications With AMPX	F. Bostelmann (ORNL), A. M. Holcomb (ORNL), D. Wiarda (ORNL), W.A. Wieselquist (ORNL)
Sensitivity Analysis and Its Convergence Through Monte Carlo Calculations for the UAM GEN-III Benchmark: Application to Power Distributions	P. Lopez (Univ. Grenoble-Alpes), A. Bidaud (Univ. Grenoble-Alpes)
Revisiting the Lockwood Albedo Measurements for Validation of the Integrated Tiger Series Electron-Photon Transport Code	Rowdy Davis (Univ. of New Mexico), Ronald P. Kensek (Sandia), Christopher M. Perfetti (Univ. of New Mexico), Aaron Olson (Sandia)
Uncertainty Quantification and Sensitivity Analysis of PWR FA Decay Heat by STREAM/RAST-K	Jaerim Jang (Ulsan Nat'l Institute of Science and Technology), Chidong Kong (Ulsan Nat'l Institute of Science and Technology), Bamidele Ebiwonjumi (Ulsan Nat'l Institute of Science and Technology), Yunki Jo (Ulsan Nat'l Institute of Science and Technology), Alexey Cherezov (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)
Acceleration of Nodal Diffusion Calculations Using Machine Learning-Driven Generation of Homogenized Macroscopic Cross-Sections	Siarhei Dzianisau (Ulsan Nat'l Institute of Science and Technology), Jiwon Choe (Ulsan Nat'l Institute of Science and Technology), Alexey Cherezov (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)
Developing Covert Cognizance (C2) for Industrial Control Systems	Arvind Sundaram (Purdue Univ.), Hany S. Abdel-Khalik (Purdue Univ.)
Application of Deep Neural Networks for Coarse Mesh Turbulence Modeling in Reactor Transients Analysis	Yang Liu (ANL), Rui Hu (ANL), Prasanna Balaprakash (ANL), Acacia Brunett (ANL), Aleksandr Obabko (ANL)
A Phase Field Model for Hydrothermal Corrosion in Silicon Carbide	Anant Raj (NC State Univ.), Jacob Eapen (NC State Univ.)
Phononica: A Phonon Dynamics Simulator	Anant Raj (NC State Univ.), Jacob Eapen (NC State Univ.)

Poster Lightning Talks: Computational Tools for Reactor Physics Applications

Go to session page

Poster Title	Authors
Benchmarking a Pronghorn Model of the Natural Convection Shutdown Heat Removal Test Facility Against STAR-CCM+	Sebastian Schunert (INL), Ramiro Freile (Texas A&M Univ.), Logan Harbour (Texas A&M Univ.), Paolo Balestra (INL)
Control Rod History Effect Assessment in a Soluble Boron-Free S-PWR	P. Devaux (CEA), M. Guyot (CEA), J.-F. Vidal (CEA)
PARAGON2/ANC Analysis of BEAVRS Benchmark Reactor Core	Mohamed Ouisloumen (Westinghouse Electric Co.), Ho Q. Lam (Westinghouse Electric Co.), Jie P. Lu (Westinghouse Electric Co.)
Validation of the High-Resolution Code nTRACER Against VVER-1000 Hot Zero Power Measurements	Marianna Papadionysiou (Paul Scherrer Institut), Seongchan Kim (Seoul Nat'l Univ.), Mathieu Hursin (Paul Scherrer Institut), Alexander Vasiliev (Paul Scherrer Institut), Hakim Ferroukhi (Paul Scherrer Institut), Han Gyu Joo (Seoul Nat'l Univ.), Andreas Pautz (Paul Scherrer Institut)
FRENDY/MG: A Multi-Group Cross Section Generation Module Using ACE Pointwise Cross Sections	Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Basma Fouad (Nagoya Univ.), Go Chiba (Hokkaido Univ.), Kenichi Tada (Japan Atomic Energy Agency)
Towards an Efficient and Stable Hybrid Transport-Depletion Sequence Using Reduced-Order Solutions at Substeps	Andrew Johnson (Georgia Institute of Technology), Dan Kotlyar (Georgia Institute of Technology)
Comparative Study for Load-Follow Operations of the Holos Microreactor	Sooyoung Choi (Univ. of Michigan), Shai Kinast (Univ. of Michigan), Claudio Filippone (HolosGen), Brendan Kochunas (Univ. of Michigan)
Validation of the GeN-Foam Model of the CROCUS Experimental Reactor	Tom Mager (Ecole Polytechnique Federale de Lausanne), Carlo Fiorina (Ecole Polytechnique Federale de Lausanne), Mathieu Hursin (Paul Scherrer Institute), Andreas Pautz (Paul Scherrer Institute)
Development of a Syntactic Validation Capability for the Use of MCNP	Peter J. Kowal (Rensselaer Polytechnic Institute), Jonathan A. Eugenio (Rensselaer Polytechnic Institute), Kurt A. Dominesey (Rensselaer Polytechnic Institute), Wei Ji (Rensselaer Polytechnic Institute), Robert A. Lefebvre (ORNL), Forrest B. Brown (LANL)
Monte Carlo Analysis of Sub-Pin Resolved Power Behaviour in Modern BWR Assembly Designs	Mathieu Hursin (Paul Scherrer Institut), Alexander Vasiliev (Paul Scherrer Institut), Dimitri Rochman (Paul Scherrer Institut), Abdelhamid Dokhane (Paul Scherrer Institut), Hakim Ferroukhi (Paul Scherrer Institut)
Operational Characteristics of Low-Enriched Moderated and Unmoderated Space Nuclear Propulsion Reactors	Matt Krecicki (Georgia Institute of Technology), Dan Kotlyar (Georgia Institute of Technology)
Development of a Griffin Reactor Physics Analysis Code Model for the Versatile Test Reactor	Nicolas Martin (INL), Ryan Stewart (INL), Zhiwen Xu (INL), Sam Bays (INL)
Numerical Investigation of Solidification of Corium in an Initially Emptied Vertical Pipe	Alex Pegarkov (Carleton Univ.), Shawn Somers-Neal (Carleton Univ.), Abubaker Alatrash (Carleton Univ.), Edgar Matida (Carleton Univ.), Vinh Tang (Carleton Univ.), Tarik Kaya (Carleton Univ.)
Validation of the Resonant Scattering Treatment in the Different APOLLO3 Self-Shielding Models	Jean-François Vidal (CEA), Madeleine Gilly (CEA)

Last modified September 22, 2021, 2:02pm EDT