gavin@ridleygav.in:~$ bibtex --list

Publications

thesis

• 2024
  GPU-Oriented Algorithms for Continuous Energy Monte Carlo Neutron Transport

  G. Ridley. PhD thesis, advisor Benoit Forget.

  Massachusetts Institute of Technology, Department of Nuclear Science and Engineering

  pdfdefense slides

journal articles

• 2026
  An Alternative to Probability Tables for Modeling Unresolved Resonance Behavior

  G. Ridley, B. Forget

  Nuclear Science and Engineering, published online February 2026

  doicontext
• 2026
  Direct Sampling of the Egelstaff-Schofield Scattering Law and the Phonon Sampling Method for Liquids

  G. Ridley, B. Forget

  Nuclear Science and Engineering, published online February 2026

  doi
• 2023
  Resonance Scattering Treatment with the Windowed Multipole Formalism

  G. Ridley, B. Forget, T. Burke

  Nuclear Science and Engineering

  doipreprint
• 2021
  A Simple Method for Rejection Sampling Efficiency Improvement on SIMT Architectures

  G. Ridley, B. Forget

  Statistics and Computing 31(3), 30

  doi
• 2021
  Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh

  D. R. Gaston, B. Forget, K. S. Smith, L. H. Harbour, G. K. Ridley, G. G. Giudicelli

  Nuclear Technology 207(7), 931–953

  doi
• 2020
  SerpentTools: A Python Package for Expediting Analysis with Serpent

  A. E. Johnson, D. Kotlyar, S. Terlizzi, G. Ridley

  Nuclear Science and Engineering 194(11), 1016–1024

  doicode
• 2018
  Introduction to Moltres: An Application for Simulation of Molten Salt Reactors

  A. Lindsay, G. Ridley, A. Rykhlevskii, K. Huff

  Annals of Nuclear Energy 114, 530–540

  doicode
• 2017
  A Method for Predicting Fuel Maintenance in Once-through MSRs

  G. Ridley, O. Chvala

  Annals of Nuclear Energy 110, 265–281

  doi

conference papers

• 2023
  Expanding the Extrapolation Limits of Neural Network Force Fields using Physics-Based Data Augmentation

  Y. Orlova, G. Ridley, F. Zhao, R. Gómez-Bombarelli

  ICLR 2023, ML4Materials workshop

  workshop
• 2022
  Topologically Optimal Nuclear Core Designs Using Deterministic Neutronics

  G. Ridley, L. Venneri, B. Forget

  ANS Annual Meeting, Anaheim, CA

  pdfslidesvideo
• 2022
  Toward Portable GPU Acceleration of the OpenMC Monte Carlo Particle Transport Code

  J. R. Tramm, P. K. Romano, J. Doerfert, A. L. Lund, P. C. Shriwise, A. Siegel, G. Ridley, A. Pastrello

  PHYSOR 2022, Pittsburgh, PA
• 2022
  Performance Improvements of the Windowed Multipole Formalism using a Rational Fraction Approximation of the Faddeeva Function

  B. Forget, J. Yu, G. Ridley

  PHYSOR 2022, Pittsburgh, PA
• 2022
  Transient MOC with Frequency Transform and DSA on Unstructured Mesh

  G. Ridley, L. H. Harbour, B. Forget, D. Gaston

  PHYSOR 2022, Pittsburgh, PA
• 2021
  Design and Optimization of GPU Capabilities in OpenMC

  G. Ridley, B. Forget

  ANS Winter Meeting, Washington, D.C.

  poster
• 2018
  Concept Reactor for Extraterrestrial Surface Power: PULSR

  D. Floyd, G. Ridley, P. Tidwell, W. Tebbs

  Transactions of the American Nuclear Society 119, 62–65
• 2017
  Preliminary Results of Material Flow Controlled MSR Depletion Calculations

  G. Ridley, O. Chvala

  Transactions of the American Nuclear Society 116, 1162–1164

talks and teaching materials

• 2023
  OpenMC Workshop

  ANS Student Conference, April 2023

  introCSGdepletion
• 2021
  Monte Carlo Neutron Transport on GPUs

  Poster

  pdf