ICRS15-RPSD2026

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15^th International Conference on Radiation Shielding and
23rd ANS Topical Meeting of the Radiation Protection and Shielding Division

2026.10.25. Sun ~ 10.29. Thu

LOTTE HOTEL JEJU

Workshop/Tutorial

2026.10.25 (Sun) full day or half day

W1 Full-Day	Hands-on Unstructured Mesh Tutorial Using MCNP6.3 and Silver Fir Software Tools This full-day hands-on tutorial, hosted by Los Alamos National Laboratory (LANL) and Silver Fir Software, introduces an advanced unstructured mesh radiation transport workflow using MCNP6.3 and Silver Fir Software tools. Participants will gain practical experience in model preparation, meshing, variance reduction, and solution visualization. Temporary software licenses will be provided, except for MCNP6.3, which participants should obtain separately. View Details Morning Session Introduction to Unstructured Mesh Workflows With the MCNP Code and Silver Fir Software Tools Example Model Review CSG to CAD Conversion using Tamarack Approaching Model Geometry Preparation and Meshing Preparing Meshes and MCNP6.3 Calculations using Attila4MC Afternoon Session Introduction to Deterministic Variance Reduction Methods Deterministic Weight Window Generation using Cottonwood Unstructured Mesh Calculation Using MCNP6.3 Solution Visualization using Tecplot Closing Remarks and Open Discussion Software Notice ※ Temporary software licenses will be provided for all required software except MCNP6.3, which participants should obtain separately.
W2	PHITS Tutorial PHITS is a general-purpose Monte Carlo particle transport simulation code developed through international collaboration led by the Japan Atomic Energy Agency (JAEA). It simulates the transport of nearly all particles—including neutrons, protons, heavy ions, photons, and electrons—across wide energy ranges (from 10-5 eV up to 1 TeV).
W3	TopMC Tutorial TopMC is a multi-functional program for neutronics calculation, nuclear design, and safety evaluation. It is the updated version of SuperMC, focusing on high-efficiency particle transport simulations.
W4	XSUN/SUSD3D Computer Package for Nuclear Data Sensitivity and Uncertainty Analysis The XSUN/SUSD3D computer code package is a specialized software suite used for deterministic neutron/gamma (n/γ) sensitivity and uncertainty (S/U) analysis. It is designed to evaluate how uncertainties in nuclear data (such as cross-sections) affect calculations of radiation transport in shielding and reactor core applications. View Details Presenter Ivan Kodeli, UKAEA, Culham, UK Ivan.kodeli@ukaea.uk Code System SUSD3D/XSUN is a code system for deterministic neutron/gamma cross-section sensitivity and uncertainty analysis. SUSD3D uses generalized perturbation theory to calculate sensitivity coefficients and standard deviations in detector responses or reactor design parameters due to input cross sections and their uncertainties. Applications and Demonstration Reaction rates, neutron/gamma fluxes and doses, k-eff, and beta-effective calculations Complex 1D, 2D, and 3D shielding and criticality problems Uncertainties from neutron/gamma multi-group cross sections, energy-dependent response functions, secondary angular distribution (SAD), and secondary energy distribution (SED) Test cases including criticality, beta-effective, fission, fusion, and accelerator (<50 MeV) shielding for both neutron and gamma S/U Package and Data SUSD3D is available from the NEA Data Bank as part of the XSUN-2023 Windows interface, developed to assist users in preparing input cards and rapidly modifying and executing the complete code chain including TRANSX, PARTISN, and SUSD3D. A recently updated version of the package will be presented. Multigroup cross sections and covariance matrices in COVFIL, COVERX, and BOXR formats are included, with different energy structures and evaluations such as JEFF-3.3 and JEFF-4, ENDF/B-VII.4, ENDF/B-VIII.0, ENDF/B-VIII.1, JENDL-5.0, FENDL-3.2, CENDL-3.2, and IRDFF-II. New capabilities and options will also be presented, and SUSD3D can accept direct and adjoint fluxes from PARTISN and DORT/TORT transport solvers.
W5	Workshop for Radiation Transport Simulation Developers (RTS2026) The NEA Expert Group on the Physics of Reactor Systems (EGPRS) organized a workshop to foster exchanges among radiation transport simulation developers. The workshop aimed to facilitate exchanges among different code developer teams encompassing both scientific and commercial developers engaged in various radiation transport (RT) applications.
W6	FLUKA Monte Carlo Workshop FLUKA is a general-purpose Monte Carlo code used for simulating the interaction and transport of hadrons, leptons, photons, and nuclei across a wide energy range in complex geometries. The workshop will provide an overview of the FLUKA code, an interactive demonstration, and hands-on exercises including geometry, scoring, and dosimetric calculations using ICRP adult mesh phantoms.
W7	ICRP Mesh-type Reference Computational Phantoms Aligned with the next General Recommendations of the International Commission on Radiological Protection (ICRP), the ICRP Task Group 103 have recently completed the development of the ICRP mesh-type reference computational phantoms (MRCPs) series for adults, children, and pregnant females (mother and fetus). This workshop will introduce the new ICRP reference phantoms, highlighting the backgrounds and rationales, overviewing the construction processes and the phantom characteristics, and demonstrating how to use the MRCPs in Monte Carlo radiation transport codes for dose calculations.
W8	PHITS-Attila4MC Coupled Shielding Calculation: Introduction and Hands-on Tutorial The PHITS-Attila4MC coupled shielding calculation method combines the precision of the Particle and Heavy Ion Transport Code System (PHITS) with the advanced variance reduction capabilities of Attila4MC, designed to efficiently solve deep penetration radiation shielding problems, particularly those involving complex CAD geometries.
W9 Full-Day	Status of Advanced SMR Development and Commercialization We are pleased and sincerely grateful that leading advanced SMR organizations, including GIF (Generation IV International Forum), ARC Clean Technology, X-energy, NANO Nuclear Energy, Saltfoss Energy, and KAERI (Korea Atomic Energy Research Institute), have kindly agreed to present their latest SMR development and commercialization status at the Advanced SMR Workshop during the ICRS15 & ANS RPSD 2026. This workshop will provide a meaningful platform for global leaders from industry, research institutes, utilities, and academia to exchange perspectives on advanced reactor technologies, licensing, commercialization pathways, and future clean energy applications. We deeply appreciate the participation and support of these distinguished organizations and look forward to productive discussions and stronger international collaboration in Jeju, Korea View Details Chair Jeongik Lee (KAIST) Theme AI, Energy, and Advanced SMRs: Shaping the Future Infrastructure Workshop Overview The Advanced SMR Workshop will bring together leading international organizations, reactor developers, utilities, and research institutes to discuss the latest progress in Generation IV Small Modular Reactors (SMRs) and future clean energy systems. The workshop will highlight commercialization strategies, licensing pathways, fuel cycle technologies, maritime applications, AI-driven energy infrastructure, and global partnership opportunities for advanced reactors. Confirmed Participating Organizations Generation IV International Forum (GIF) Korea Atomic Energy Research Institute (KAERI) ARC Clean Technology X-energy Saltfoss Energy NANO Nuclear Energy Additional speakers and organizations will be announced in due course.

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