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15th 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
Laptops and the MCNP Code will not be provided. All attendees wishing to “click along” with the exercises will be provided with access to the Silver Fir Software tools. Users are encouraged to bring their own CAD and/or CSG models with them should they wish to see software and workflows demonstrated on their models.
View Details
Presenters
  • Tanner Hall (TH) – Los Alamos National Laboratory
  • Andrew Cooper (AC) – Silver Fir Software
Programme (10:00–16:30)
Morning Session
TimeProgrammePresenter
10:00–10:15Welcome and IntroductionsTH-AC
10:15–10:45Software SetupAC
10:45–11:10Introduction to Unstructured Mesh Workflows with the MCNP Code and Silver Fir Software ToolsTH-AC
11:10–11:35Example Model ReviewAC
11:35–11:50☕ Coffee Break (15 min)—
11:50–12:20CSG to CAD Conversion using TamarackAC
12:20–12:50Approaching Model Geometry Preparation and MeshingTH
12:50–13:30Preparing Meshes and MCNP6.3 Calculations using Attila4MCAC
13:30–14:15Lunch Break (45 min)—
Afternoon Session
TimeProgrammePresenter
14:15–14:45Introduction to Deterministic Variance Reduction MethodsTH
14:45–15:25Deterministic Weight Window Generation using CottonwoodAC
15:25–15:40☕ Coffee Break (15 min)—
15:40–16:05Unstructured Mesh Calculation Using MCNP6.3AC
16:05–16:15Solution Visualization using TecplotTH
16:15–16:30Closing Remarks and Open Discussion—
Participant Preparation
Laptops and the MCNP Code will not be provided. All attendees wishing to “click along” with the exercises will be provided with access to the Silver Fir Software tools. Users are encouraged to bring their own CAD and/or CSG models with them should they wish to see software and workflows demonstrated on their models.
W2
Morning Session
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).
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Time Program
09:00-09:30 General Introduction to PHITS
09:30-10:00 Recent Improvements in PHITS: Highlighting AI-Agent-Driven Usage
10:00-12:00 Hands-on Session: Learning How to Use PHITS Through Radiation Range Calculations
Speakers
  • Dr. Tatsuhiko Sato, Japan Atomic Energy Agency
  • Dr. Takuya Furuta, Japan Atomic Energy Agency
  • Dr. Tatsuhiko Ogawa, Japan Atomic Energy Agency
Note
Participants are encouraged to bring a laptop PC with the latest version of PHITS installed.
Non-PHITS users are also welcome to join and learn how to use PHITS via its web version.
W3
Afternoon Session
New Release of TopMC, Usage & Technical Exchange
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.
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Time Program
14:25-14:55 New version launch and general introduction of TopMC
15:00-15:30 Sharing of practical experience in using TopMC
15:30-16:30 TopMC operation training
Speaker
  • Shanqi Chen, FDS (Anhui) Technology Co., Ltd.
W4
Morning Session
SUSD3D/XSUN-2026: A WINDOWS code system for Deterministic n/γ Cross-Section Sensitivity and Uncertainty (S/U) 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.
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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-4.0, 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. SUSD3D code can accept direct and adjoint fluxes from PARTISN, DORT/TORT transport solvers.

Programme (09:00–12:00)

General Introduction to XSUN-2026 (09:00–10:00)

  • SUSD3D code: method and available features
  • XSUN computer code environment, running the suite of transport and S/U codes, examples of applications (criticality, kinetics, shielding, neutron and gamma S/U)
  • Nuclear cross sections and covariance matrices available in the package
  • Pitfalls of covariance matrix processing, mathematical V&V of covariances, processing using NJOY and PUFF-4 codes, and differences between COVFILS, BOXR (NJOY), and COVERX (PUFF-4) formatted data
  • Intercomparison with other codes (Serpent, TSUNAMI, MCSEN, ERANOS): keff, βeff (SNEAK) and shielding (KFK, FNG benchmark) applications

Hands-on Session (10:00–12:00): Running the suite of codes on 1D, 2D, and 3D criticality and shielding test cases

Software Availability

XSUN-2026 system and SUSD3D code will be made available to workshop participants.

Please note that the TRANSX and PARTISN codes must be obtained separately from the NEA Data Bank or RSICC.

For participants who do not have TRANSX and PARTISN installed, binary output files will be provided to allow basic SUSD3D test case exercises.

Note that XSUN-2026 runs on WINDOWS environment only.
W6
Afternoon Session
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.

Participants are expected to bring their own laptop and to verify beforehand that the latest versions of both FLUKA and Flair have been installed, so that they can participate in the practical sessions.

Do not forget that you should be a registered FLUKA.CERN user in order to download the code and participate in the course. You can find the relevant instructions here https://fluka.cern/download/registration
View Details
Time Program
14:00-14:10 FLUKA Introduction
Short introduction of FLUKA and flair capabilities
14:10-14:30 Basic input
FLUKA input creation with flair and running (Interactive / follow-along)
14:30-14:45 Basic Geometry
Principles of combinatorial geometry and how to build, visualize and debug in flair geometry editor (Interactive / follow-along)
14:45-15:00 Scoring
Basic concepts of scoring/tallies in FLUKA
15:00-15:50 Hands-on
Student exercise time, building an input, running and getting some basic results. Last 5min will be devoted on the solution of the exercise.
15:50 Break
16:00-16:15 Radiation Protection - live demo
Activation and residual radiation as well decay evolution in a single run
16:15-16:30 Unstructured Mesh - live demo (Interactive / follow-along)
How to import CAD geometries and common pitfalls
16:30-16:40 ICRS phantom - live demo (Interactive / follow-along)
Import the adult mesh-type reference computational phantom and use in FLUKA
16:40-17:30 Hands-on
Student exercise time, load the ICRS unstructured mesh phantom, define an external irradiation scenario, and score the dose to organs. Last 5min will be devoted on the solution of the exercise.
17:30-17:45 Cross-validation with other Monte Carlo codes
Using flair capabilities to run other Monte Carlo codes (Phits/OpenMC) from the same FLUKA master input file (Interactive / follow-along)
17:45-17:55 Advanced topics
Description of advanced subjects in FLUKA
17:55-18:00 Closing
Speakers
  • Claudia Ahdida, CERN
  • Claudio Cipriani, CERN
  • Dominika Wasik, CERN
  • Giorgio Gariaschelli, CERN
  • Tommaso Lorenzon, CERN
  • Vasilis Vlachoudis, CERN
W7
Full-Day
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.
View Details
Time Workshop Title & Details Presenter
08:30-09:00 Introduction to ICRP Mesh Phantoms
Concepts and historical development of computational phantoms; necessity and significance of developing ICRP mesh phantoms
 Chan Hyeong Kim
09:00-09:45 Development Process and Key Features of ICRP Mesh Phantoms: Adult Phantoms
Introduction to the development process and characteristics of ICRP adult mesh phantoms
 Yeon Soo Yeom
09:45-10:30 Development Process and Key Features of ICRP Mesh Phantoms: Pediatric Phantoms
Introduction to the development process and characteristics of ICRP pediatric mesh phantoms
 Chansoo Choi
10:30-11:15 Development Process and Key Features of ICRP Mesh Phantoms: Pregnant and Fetal Phantoms
Introduction to the development process and characteristics of ICRP pregnant and fetal mesh phantoms
 Bangho Shin
11:15-12:00 Applications of ICRP Mesh Phantoms
Introduction to various applications and extensions of ICRP mesh phantoms for environmental and medical exposure purposes
 Sungho Moon
12:00-14:00 Lunch
14:00-14:45 Understanding ICRP Mesh Phantom Data and Theoretical Background for Dose Assessment
Understanding the structural format of ICRP mesh phantom data and the theoretical background for organ and effective dose calculations
 Suhyeon Kim
14:45-15:30 Applications of ICRP Mesh Phantoms Using the PHITS Code
Methods for implementing ICRP mesh phantoms in the PHITS code and performing dose assessments
 Chansoo Choi
15:30-16:15 Applications of ICRP Mesh Phantoms Using the MCNP6 Code
Methods for implementing ICRP mesh phantoms in the MCNP6 code and performing dose assessments
 Bangho Shin
16:15-17:00 Applications of ICRP Mesh Phantoms Using Geant4
Methods for implementing ICRP mesh phantoms in Geant4 and performing dose assessments
 Sungho Moon
17:00-17:45 Monte Carlo Simulation Code for External Exposure (McSEE)
Introduction and live demonstration of the McSEE software for external dose assessment in emergency situations
 Hyeonil Kim
W8
Afternoon Session
PHITS–Attila4MC Coupled Shielding Calculation Workshop
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.
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Time Program
13:30-13:45 Introduction to Silver Fir Software: Company Overview, Products, and PHITS Integration
13:45-14:15 CAD Model Preparation for PHITS
14:15-14:45 Meshing for PHITS in Attila4MC
14:45-15:15 PHITS Calculation Preparation
15:15-16:00 Deterministic Variance Reduction for PHITS Using Attila4MC-Cottonwood
16:00-16:30 Solution Visualization for PHITS Using Tecplot
Note
Participants are encouraged to bring a laptop PC with PHITS installed.
Silver Fir Software will provide evaluation licenses of Attila4MC for participants who wish to follow the hands-on exercises.
To prepare the evaluation licenses, the attendee list should be provided no later than three weeks before the workshop.
W9
Full-Day
Status of Advanced SMR Development and Commercialization
AI, Energy, and Advanced SMRs: Shaping the Future Infrastructure
Co-hosted by Korea Hydro & Nuclear Power(KHNP)
View Details
Theme
  • AI, Energy, and Advanced SMRs: Shaping the Future Infrastructure
Host
  • Co-hosted by Korea Hydro & Nuclear Power(KHNP)
Moderator/Chair
  • Jeongik Lee(KAIST)
Time Affiliate Subject Presenter
09:30-10:00 Registration
10:00-10:30 Innovative Small Modular Reactor Development Agency Development status of i-SMR Sang Gyu Lim
10:30-11:00 KAERI Overview of Generation IV International Forum (GIF) and Korea's Participation Jin-Young Cho
11:00-11:30 Coffee Break
11:30-12:00 KAERI Status of Korean SFR-based SMR Development Jewhan Lee
12:00-12:30 ARC Clean Technology Introduction to ARC Clean Technology & Collaboration with Korean/Global Partners James Wolf
12:30-14:00 Lunch
14:00-14:30 KAERI / NST Current Status of Molten Salt Reactor-Based SMR Ship Development Dong-Hyoung Lee
14:30-15:00 Saltfoss Energy Development status and shielding design of the seaMSR-100 Esben Klinkby
15:00-15:30 Coffee Break
15:30-16:00 KAERI HECTAR: High Temperature Gas-cooled Reactor for Industrial Process Heat Chan Soo Kim
16:00-16:30 NANO Nuclear Energy Building the Future of Energy and Power James Walker
16:30-16:45 Coffee Break
16:45-17:45 Panel Discussion
Speakers
  • Sang Gyu Lim, Innovative Small Modular Reactor Development Agency
  • Jin-Young Cho, KAERI
  • Jewhan Lee, KAERI
  • James Wolf, ARC Clean Technology
  • Dong-Hyoung Lee, KAERI / NST
  • Esben Klinkby, Saltfoss Energy
  • Chan Soo Kim, KAERI
  • James Walker, NANO Nuclear Energy
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