International Conference on Physics of Reactors (PHYSOR 2024)

Full Issue

Reactor Pressure Vessel Characterization Methods Development for the High Flux Isotope Reactor to Support Future Vessel Replacement

D. Chandler (ORNL), K. Burg (ORNL)

Californium-252 Production Validation Studies at the High Flux Isotope Reactor with Campaign 78 Data

D. Hartanto (ORNL), D. Chandler (ORNL), G. Power (ORNL), J. Bae (ORNL), K. Burg (ORNL)

Prediction of the TREAT Facility Power and Temperature of Sirius-2c Nuclear Propulsion Fuel Experiment

Mustafa K. Jaradat (INL), Sebastian Schunert (INL), Frederick N. Gleicher (INL), Mark DeHart (INL)

Testing and Implementation of 6% Enriched UO2 Fuel at the PULSTAR Reactor

N.C. Fleming (NCSU), A.I. Hawari (NCSU)

Current Status of the Water Activation Loop at JSI TRIGA Reactor

D. Kotnik (Jožef Stefan Institute), J. Peric (Jožef Stefan Institute), L. Snoj (Jožef Stefan Institute), I. Lengar (Jozef Stefan Institute)

Application of Monte Carlo Solver Solomon to Critical Mass Calculation of Fuel Randomization System

Tomoaki Watanabe (Japan Atomic Energy Agency), Taro Ueki (Japan Atomic Energy Agency), Kenya Suyama (Japan Atomic Energy Agency)

Statistical Error Estimation of Autocorrelation Method Using Circular Block Bootstrap Method

Ryoga Hirota (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Kenichi Watanabe (Kyushu Univ.), Junichi H. Kaneko (Hokkaido Univ.)

Sensitivities of Configurations with Missing Fuel Rods

Benjamin Dechenaux (IRSN)

Investigation of Subcriticality Monitoring Method Using Improved Simplest Reactivity Estimator with Bilateral Filter

Taiyo Moribe (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Junichi H. Kaneko (Hokkaido Univ.)

Evaluation of Thermal Scattering Law for U3Si2 Using Temperature-Dependent Phonon Density of States

Junhyoung Gil (NCSU), Ayman I. Hawari (NCSU)

Sub-Critical Gamma Noise Measurements in the CROCUS Zero-Power Reactor

F.B. Darby (Univ. Michigan), O.V. Pakari (École Polytechnique Fédérale de Lausanne), M.Y. Hua (Univ. Michigan), V.P. Lamirand (École Polytechnique Fédérale de Lausanne), S.D. Clarke (Univ. Michigan), A. Pautz (École Polytechnique Fédérale de Lausanne), S.A. Pozzi (Univ. Michigan)

Adding New Experimental Capacities to the CABRI Nuclear Reactor

D. Bonvalet (CEA), F. Rodiac (CEA)

Neutron Noise Measurements of a Fast HEU Copper System

Cole Kostelac (LANL), Robert Weldon (LANL), Nicholas Whitman (LANL), Nicholas Thompson (LANL), Theresa Cutler (LANL), Ayodeji Alajo (Missouri Univ. Science and Technology)

Capturing Reactor Pulse Characteristics: Cherenkov Power Meter in JSI TRIGA Pulse Experiments and Pulse Database

Julijan Peric (Jozef Stefan Institute), Ingrid Svajger (Jozef Stefan Institute), Vladimir Radulovic (Jozef Stefan Institute), Luka Snoj (Jožef Stefan Institute)

Measurement of the Prompt Decay Constant in a Zero Power Reactor Using a Novel 3D Detector System

Michel Saliba (École Polytechnique Fédérale de Lausanne), Oskari Pakari (École Polytechnique Fédérale de Lausanne), Wilfried Monange (IRSN), Andreas Pautz (École Polytechnique Fédérale de Lausanne), Vincent Lamirand (École Polytechnique Fédérale de Lausanne)

Reactivity Relative Monitoring Using Threshold Fission Chambers with the Current-to-Flux Method for the Accelerator Driven VENUS-F Subcritical Reactor

N. Marie (Normandie Univ.), A. Billebaud (Univ. Grenoble Alpes), S. Chabod (Univ. Grenoble Alpes), A. Kochetkov (SCK CEN), A. Krása (SCK CEN), F.-R. Lecolley (Normandie Univ.), J.-L. Lecouey (Normandie Univ.), G. Lehaut (Normandie Univ.), N. Messaoudi (SCK CEN), G. Vittiglio (SCK CEN), J. Wagemans (SCK CEN)

Epithermal Neutron Spectrum Filtering Experiment Design at the VENUS-F Zero Power Fast Reactor

Federico Grimaldi (SCK CEN), Patrick Blaise (Framatome), Antonin Krasa (SCK CEN), Pierre-Etienne Labeau (Univ. Libre de Bruxelles), Guido Vittiglio (SCK CEN), Jan Wagemans (SCK CEN)

Understanding the Moderator Temperature Coefficient of Reactivity of Prismatic Graphite-Moderated Gas-Cooled Reactors with Burnable Absorbers

D. Bazzani (Politecnico di Milano), S. Wijaya (KAIST), A. Cammi (Politecnico di Milano), Y. Kim (KAIST)

A Data-Driven Incident Detection Method for the Safe Operation of Molten Salt Fast Reactors

N. Abrate (Politecnico di Torino), N. Caruso (Politecnico di Torino), S. Dulla (Politecnico di Torino), S. Lorenzi (Politecnico di Milano), N. Pedroni (Politecnico di Torino)

Transient Modeling and Simulation for Deimos, an Advanced Reactor Experiment

Alexis Maldonado (LANL), Theresa E. Cutler (LANL), Kristin N. Stolte (LANL), Holly R. Trellue (LANL)

Pulsed Neutron Experiments in the Inherently Safe Subcritical Assembly

D. Siefman (LLNL), W. Zywiec (LLNL), C. Percher (LLNL), D. Heinrichs (LLNL)

Critical Experiment Plans on the New STACY to Clarify the Criticality Characteristics of the Molten Core-Concrete Interaction Products

Satoshi Gunji (Japan Atomic Energy Agency), Shouhei Araki (Japan Atomic Energy Agency), Kazuhiko Izawa (Japan Atomic Energy Agency), Kenya Suyama (Japan Atomic Energy Agency)

Designing a Deimos-Based Microreactor Criticality Experiment with MCNP and Whisper

Alexis Maldonado (LANL), Keenan J. Hoffman (LANL), Kristin N. Stolte (LANL), Christopher Perfetti (Univ. New Mexico), Theresa E. Cutler (LANL), Holly R. Trellue (LANL)

The National Criticality Experiments Research Center: Capability Expansion and Experiments in the Last Three Years

George E. McKenzie (LANL), Theresa E. Cutler (LANL), Travis J. Grove (LANL), Jesson D. Hutchinson (LANL), Juliann R. Lamproe (LANL), Nicholas W. Thompson (LANL), Nicholas H. Whitman (LANL), Joetta M. Goda (LANL)

Hermes Reactor Demonstration, Initial Startup and Physics Testing

N. Satvat (Kairos Power), K. Riley (Kairos Power), F. Vitullo (Kairos Power), R. Hernandez (Kairos Power), M. Fratoni (Univ. California, Berkeley), B. Haugh (Kairos Power), E. Blandford (Kairos Power)

Experiments at the JSI TRIGA Research Reactor for Validation of Nuclear Fuel Depletion Calculations

Anže Pungerčič (Jožef Stefan Institute), Vladimir Radulovic (Jožef Stefan Institute), Alireza Haghighat (Virginia Tech), Luka Snoj (Jožef Stefan Institute)

Lead Neutron Data Validation Using Integral Experiments at the VENUS-F and BFS Zero Power Reactors

Antoine de Barsy (SCK CEN), Federico Grimaldi (SCK CEN), Anatoly Kochetkov (SCK CEN), Antonin Krasa (SCK CEN), Guido Vittiglio (SCK CEN), Marie-Laure Vuyge (SCK CEN), Jan Wagemans (SCK CEN)

High Burn-up Code Results Intercomparison on a Research Reactor Assembly Numerical Benchmark

R. Ichou (IRSN), F.X. Le Dauphin (IRSN), T. Nicol (CEA), C. Carmouze (CEA), F. Estebe (TechnicAtome)

Preparing a New Reference Neutron Field in the Graphite-Shaped Reference LR-0 Reactor Core

Tomáš Peltan (Research Centre Rez), Tomáš Czakoj (Research Centre Rez), Eva Vilímová (Univ. West Bohemia), Jan Šimon (Research Centre Rez), Vlastimil Juříček (Research Centre Rez), Michal Košťál (Research Centre Rez)

Measurement of the High Energy Gamma Spectrum up to 13 MeV in the Special Core of the LR-0 Reactor

Michal Kostal (Research Center Rez), Tomas Czakoj (Research Center Rez), Tomas Peltan (Research Center Rez), Evzen Losa (Research Centre Rez), Martin Schulc (Research Center Rez), Vlastimil Juricek (Research Centre Rez), Jan Šimon (Research Center Rez), Vojtěch Rypar (Research Center Rez), Filip Mravec (Masaryk Univ.), František Cvachovec (Univ. Defence), Zdenek Matej (Masaryk Univ.), Roberto Capote (IAEA)

NAUTILUS: A Project for the Development of Experimental Methods for Investigating Innovative Approaches to Nuclear Waste Management and to Nuclear Safety

M. Viebach (Technische Univ. Dresden), A. Knospe (Technische Univ. Dresden), C. Lange (Technische Univ. Dresden), B. Merk (Univ. Liverpool), A. Hurtado (Technische Univ. Dresden)

Preliminary Analysis of a Nuclear-Grade Sandwich Composite for Transportable Microreactor Shielding

Ryan H. Stewart (INL), Samuel E. Bays (INL), Adam X. Zabriskie (INL), Joshua N. Zelina (INL), Abderrafi M. Ougouag (INL), Robert C. O'Brien (INL)

Exploring Boron Monitoring Solutions in Pressurized Water Reactors for Enhanced Loss of Coolant Accidents Mitigation

Nouhaila Tabti (CEA), Adrien Sari (CEA), Dominique Tromson (CEA)

Reliability Assessment of Passive Nuclear Systems Influenced by Corrosion in Stratified Hot Fluids

Akmali Masood (Assystem Energy and Operation), R. Plana (Assystem Energy and Operation)

SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario

G. Radulescu (ORNL), D. Hartanto (ORNL), F. Bostelmann (ORNL), W. Wieselquist (ORNL)

An Open Source Multiphysics Workflow for the Analysis of Fusion Driven Systems

Matthew J. Nyberg (Univ. Wisconsin, Madison), Joseph T. Eickman (Univ. Wisconsin, Madison), Patrick C. Shriwise (ANL), Ben A. Lindley (Univ. Wisconsin, Madison)

Theory of Neutron Multiplicity Counting in an Energy-Dependent Transport Model

Victor Dykin (Chalmers Univ. Technology), Senada Avdic (Univ. Tuzla), Imre Pázsit (Chalmers Univ. Technology)

Development of a Steady State Reactor Physics Surrogate Model for the Idaho State University AGN-201 Digital Twin Using MOOSE

Quinton J. Williams (Oregon State), Ryan H. Stewart (INL), Todd S. Palmer (Oregon State), Camille J. Palmer (Oregon State), Chad Pope (Idaho State), Ashley Shields (INL), Christopher Ritter (INL)

Sub-Pin Fission Product Sensitivity to Assembly and Core Models on High-Burnup Fuel and Comparison to Experimental Measurements

Andrew Conant (ORNL), Mehdi Asgari (ORNL), Aaron Graham (ORNL), Greg Balco (LLNL)

Nemo: A Centralized Model Representation for Reactor Physics Solvers

P.E. Burke (Naval Nuclear Laboratory), S.J. Douglass (Naval Nuclear Laboratory), D.F. Gill (Naval Nuclear Laboratory), D.P. Griesheimer (Naval Nuclear Laboratory), M.W. Hackemack (Naval Nuclear Laboratory), B.R. Nease (Naval Nuclear Laboratory)

Assessment of Heuristics for the Automated Generation of 2D Method of Characteristics Mesh

Kyle Vaughn (Univ. Michigan), Brendan Kochunas (Univ. Michigan)

Geometric Acceleration Structures to Speed Up Cell Searches in OpenMC

Saad Amin (Mission San Jose High School), Gavin Ridley (MIT), Benoit Forget (MIT)

A Recursive Subdivision Algorithm for Delta-Tracking on Bezier Curve Geometries in SCONE

Jamie K. Edwards (Univ. Cambridge), Andrew Davis (UKAEA), Eugene Shwageraus (Univ. Cambridge)

A Delta-Tracking Method that Supports Finite-Element Material Properties in Mesh-Based Monte Carlo Codes

Pablo A. Vaquer (LANL), Michael E. Rising (LANL), Joel A. Kulesza (LANL), Colin A. Weaver (LANL), Colin J. Josey (LANL)

Impact of the Multiphysics Coupling on the Reactivity Swing and Fuel Depletion of an SFR Phenix Like Subassembly

V. Viallon (CEA), E.Y. Garcia-Cervantes (CEA), L. Buiron (CEA)

Investigation of Ring-Heterogeneous Geometry Approximation for Efficient and Practical SFR Analysis

Namjae Choi (INL), Stefano Terlizzi (INL), Yaqi Wang (INL), Hansol Park (ANL), Changho Lee (ANL), Javier Ortensi (INL)

Modeling and Validation of Axial Thermal Expansion in the ARMI Framework

Chris Keckler (TerraPower), Anthony L. Alberti (TerraPower)

Modeling of Sodium Fast Reactors Thermal Expansion Reactivity Feedback Using GeN-Foam and Serpent

Giovanni Nervi (École Polytechnique Fédérale de Lausanne), Alessandro Scolaro (École Polytechnique Fédérale de Lausanne), Mathieu Hursin (École Polytechnique Fédérale de Lausanne), Carlo Fiorina (TAMU)

Uniform and Non-Uniform Geometric Deformations in Monte Carlo with Virtual Density Theory

Anuj Dubey (Univ. Cambridge), Mikolaj Adam Kowalski (Univ. Cambridge), Eugene Shwageraus (Univ. Cambridge)

A Comparison of the Modal Expansion Method and Exact-to-Precision Generalized Perturbation Theory Capabilities in Reactor Physics

T. Sauzedde (CEA), P. Archier (CEA), F. Nguyen (CEA)

Adjoint-Based Perturbation Theory for Heat Conduction and Dynamics Coupled Multiphysics Simulations of Nuclear Reactor Transients

Alexis Maldonado (LANL), Christopher M. Perfetti (Univ. New Mexico)

Development of an Adjoint Approach for Calculating Sensitivities of Effective Kinetic Parameters in Continuous-Energy Monte Carlo Code RMC

S. Jiang (Tsinghua Univ.), K. Wang (Tsinghua Univ.), P. Shen (Tsinghua Univ.)

Bayesian Inverse Problem and Uncertainty Quantification in the Joint Analysis of Neutron and Gamma Corrrelations

Paul Lartaud (CEA), Philippe Humbert (CEA), Josselin Garnier (Institut Polytechnique de Paris)

Comparison of Bayesian Model Calibration Techniques for Future Application to Fuel Performance Behavior Models

S. Maccario (École Polytechnique Fédérale de Lausanne), A. Scolaro (École Polytechnique Fédérale de Lausanne), A. Vasiliev (Paul Scherrer Institute), M. Hursin (Paul Scherrer Institute)

An Optimization Approach to Improve Thermal Scattering Law Using Experimental Total Cross Section Data

Vaibhav Jaiswal (IRSN)

Generation of Enrichment-Dependent Thermal Neutron Scattering Data

B.K. Laramee (NCSU), N.C. Fleming (NCSU), J.P.W. Crozier (NCSU), A.I. Hawari (NCSU)

Development of Thermal Scattering Law and Cross Sections of Hydrogen in Paraffin Wax

T. Ahmed (NCSU), N.C. Fleming (NCSU), A.I. Hawari (NCSU)

Thermal Neutron Scattering Behavior of Nitrogen-Enriched Uranium Mononitride

Amelia Trainer (Naval Nuclear Laboratory), Jonathan Wormald (Naval Nuclear Laboratory), Jesse Holmes (Naval Nuclear Laboratory), Mike Zerkle (Naval Nuclear Laboratory)

Embedding Neural Thermal Scattering (NeTS) Modules in SERPENT for Higher Fidelity Advanced Reactor Analysis

Jonathan P.W. Crozier (NCSU), Ayman I. Hawari (NCSU)

Hobbes: Multigroup Cross Section Generation for Mixed-Architecture Computing Environments

S.J. Douglass (Naval Nuclear Laboratory)

Understanding the Macroscopic Cross Section Treatment in Hybrid Continuous Energy and Multigroup Depletion Using the Shift Monte Carlo Code

Vidor Lujan (Georgia Tech), Bailey Painter (Georgia Tech), Inhyung Kim (Univ. California, Berkeley), Massimiliano Fratoni (Univ. California, Berkeley), Thomas M. Evans (ORNL), Tara M. Pandya (ORNL), Dan Kotlyar (Georgia Tech)

Derivation of the History Variable Calculation for Macro-Depletion in Nodal Simulators

Thomas Folk (Univ. Michigan), Brendan Kochunas (Univ. Michigan)

Initial Assessment of Online Cross Section Generation Capability of Griffin for Gas-Cooled Pebble-Bed Reactor

Hansol Park (ANL), Yeon Sang Jung (ANL), Changho Lee (ANL), Yaqi Wang (INL), Javier Ortensi (INL)

Application of Expanded Transfer Functions for Predicting Coarse Mesh, One-Group Macroscopic Cross Sections in a 3D Realistic PWR Core

Bailey Painter (Georgia Tech), Dan Kotlyar (Georgia Tech)

Initial Validation of the SIMULATE5-K and the CMS5 Reactor Modeling Suite with the SPERT-III Experiments

William C. Dawn (Studsvik Scandpower), Gerardo Grandi (Studsvik Scandpower), Tamer Bahadir (Studsvik Scandpower)

High-Fidelity Serpent2/SCF Solutions for Rod Ejection Scenarios in Support to the Verification of the CAMIVVER APOLLO3®/CATHARE3 Coupling Prototype

L. Mercatali (Karlsruhe Institute for Technology), G. Huaccho (Karlsruhe Institute for Technology), B. Vezzoni (Framatome), B. Calgaro (Framatome), P. Mosca (CEA), F. Damian (CEA), V.-H. Sanchez-Espinoza (Karlsruhe Institute for Technology)

Computational Modeling and Verification of MSR Transients via MSRE Reactivity Insertion Tests

M. Elhareef (Virginia Commonwealth Univ.), T. Fei (ANL), Z. Wu (Virginia Commonwealth Univ.)

A Step Towards a Comprehensive Uncertainty Quatification in Transient Analysis

Evgeny Ivanov (IRSN), Antonio Sargeni (IRSN), Franck Bernard (IRSN)

ZDkin, a Neutronic Point Kinetics Code with Modular Temperature Feedback

E. Lefevre (TechnicAtome), J. Couybes (TechnicAtome), G. Kozlowski (TechnicAtome)

A Comparative Study of Efficient Sampling Techniques for Uncertainty Quantification due to Cross-Section Covariance Data

Tatsuya Fujita (Japan Atomic Energy Agency)

Nuclear Data Uncertainty Methods in CASMO5 Using ENDF/B-VIII Covariances

Joshua Hykes (Studsvik Scandpower), Charles Wemple (Studsvik Scandpower), Rodolfo Ferrer (Studsvik Scandpower)

Computation of Sensitivity in Monte-Carlo Codes: Investigation of Convergence for Reactor Cores with High Dominance Ratio

M. Rababah (LPSC), A. Bidaud (LPSC)

Uncertainty Analysis of the Reaction Rates in Ringhals

Jacob Persson (Vattenfall Nuclear Fuel)

Uncertainty Quantification in Fluoride-Based Molten Salt Reactors with Open Sourced Tools

Zsolt Elter (Uppsala Univ.), Augusto Hernandez Solis (SCK CEN), Mario Ponce Tovar (Seaborg Technologies)

Preliminary Validation of Intra-Pin Reaction Rate Predictions from the Deterministic Transport Codes GeN-Foam and MPACT

Tom Mager (École Polytechnique Fédérale de Lausanne), Kyle Vaughn (Univ. Michigan), Mathieu Hursin (École Polytechnique Fédérale de Lausanne), Brendan Kochunas (Univ. Michigan), Andreas Pautz (Paul Scherrer Institute)

Initial Benchmarking of a New ENDF/B-VIII.1.β2-Based CASMO5 Neutron Data Library

Rodolfo Ferrer (Studsvik Scandpower), Charles Wemple (Studsvik Scandpower), Joshua Hykes (Studsvik Scandpower)

Verification and Validation of the VANGARD Pinwise Nodal Code with Preliminary Analyses of BEAVRS Benchmark

Seoyoon Jeon (Seoul Nat'l Univ.), Brendan Kochunas (Univ. Michigan)

Response Matrix Benchmark for the 1D Transport Equation with Matrix Scaling

B.D. Ganapol (Univ. Arizona), J.K. Patel (Univ. Michigan)

Synthetic Perturbation as Flux Initializer for the Method of Characteristics Solver of APOLLO3®

A. Gammicchia (CEA), S. Santandrea (CEA), A. Brighenti (Framatome)

Surface Characteristics Scheme for Solving the Transport Equation in Extruded and Unstructured 3D Geometries

Arthur Le Bars (CEA), Simone Santandrea (CEA), Sandra Dulla (Politecnico di Torino)

Linear Source Approximation in the Random Ray Method

Rufus Neame (Univ. Cambridge), Paul Cosgrove (Univ. Cambridge)

Implementation of the Discontinuous Galerkin Method into FENNECS and Other New Improvements for LWR Analysis

Romain Henry (GRS), Jeremy Bousquet (GRS), Armin Seubert (GRS)

Multiphysics Simulations of the KRUSTY Criticality Experiment Using BlueCrab

Yan Cao (ANL), Yinbin Miao (ANL), Kun Mo (ANL), Nicolas Stauff (ANL), Changho Lee (ANL)

Coupled Multiphysics Modeling of Heat Pipe Microreactors Using Cardinal, BISON, and Sockeye

M. Eltawila (Univ. Illinois, Urbana-Champaign), A.J. Novak (Univ. Illinois, Urbana-Champaign), Y. Miao (ANL)

Application of Basis Projection Methods to Temperature Distribution Construction in Heat Pipe Microreactor

Dean Price (Univ. Michigan), Majdi I. Radaideh (Univ. Michigan), Brendan Kochunas (Univ. Michigan)

Multiphysics Simulation of TRISO Fuel Compacts and the Effects of Homogenization

Aya Hegazy (Univ. Illinois, Urbana-Champaign), April J. Novak (Univ. Illinois, Urbana-Champaign), Rizwan-uddin (Univ. Illinois, Urbana-Champaign)

Thermal-Mechanical Considerations for the Radiantly Integrated TPV-Microreactor System

Naiki Kaffezakis (Georgia Tech), Dan Kotlyar (Georgia Tech)

Developing a Deterministic Calculation Scheme for Perturbations of In-Core Instrumentation of an MTR-Core in Support to Bayesian Calibration

S. Lapaire (CEA), T. Bonaccorsi (CEA), J.-M. Palau (CEA)

Impact of Integral Experiments Choice for a GLLSM Data Assimilation Process: Application to Spent Fuel Pool Storage

Romain Bossoutrot (IRSN), Frédéric Fernex (CEA), Julien Taforeau (IRSN)

Results of the CAMIVVER V&V Campaign of the NEMESI Multi-Parameter Library Generator Prototype Based on APOLLO3®

M. Tiberga (EDF), B. Vezzoni (Framatome), A. Willien (EDF), A. Brighenti (Framatome), G. Huaccho Zavala (Karlsruhe Institute for Technology), N. Guler (EDF), P. Laurent (EDF), L. Mercatali (Karlsruhe Institute for Technology), P. Mosca (CEA)

Demonstration of Uncertainty Reduction for Generic Pebble-Bed Fluoride-Salt-Cooled High Temperature Reactor (gFHR)

Noah A.W. Walton (Univ. Tennessee, Knoxville), Nader Satvat (Kairos Power), Vladimir Sobes (Univ. Tennessee, Knoxville)

Analytical Description of the Neutron Up-Scattering in the Resonance Range

A. Bengoechea (CEA), G. Noguere (CEA), D. Bernard (CEA), P. Tamagno (CEA)

Implementation of Unresolved Resonance Region Probability Tables in the GNDS Format

M.-A. Descalle (LLNL), C.M. Mattoon (LLNL), M.S. McKinley (LLNL), J. Northrop (Oregon State), G. Gert (LLNL), B.R. Beck (LLNL), A. Dreyfuss (LLNL)

Improved Evaluated Nuclear Data in the Resonance Region by Combining Energy Dependent Measurements and Depletion Calculations: Application to Pu-239+n, Pu-240+n and Pu-241+n

M. Hursin (Ecole Polytechnique Fédérale de Lausanne), D. Rochman (Paul Scherrer Institute), S. van der Marck (Nuclear Research and Consultancy Group)

On the Possible use of Propagation of Resonance Parameters Uncertainties Using the R-Matrix Formalism

Pierre Sole (IRSN), Vaibhav Jaiswal (IRSN), Cédric Jouanne (CEA)

Predicting (n,2n) Cross Sections Using Machine Learning

Rohan Gaya (Univ. Cambridge), Valeria Raffuzzi (Univ. Cambridge), Eugene Shwageraus (Univ. Cambridge), Lee Morgan (AWE)

Comparison of Two Infinite Homogeneous Medium Ultra Fine Group Neutron Slowing-Down Solvers in APOLLO3®

Terry Levy (CEA), Li Mao (CEA), Richard Sanchez (CEA), Emeline Rosier (CEA), Igor Zmijarevic (CEA), Stéphane Mengelle (CEA), Cédric Jouanne (CEA), Odile Petit (CEA)

A Collision Probability Formulation of the Resonance Spectrum Expansion (RSE) Self-Shielding Method

Alain Hebert (Institut de Genie Nucleaire)

A Generalized Differential Equation and Numerical Method for the Standard and Deformed Doppler Broadening Functions

Willian Vieira de Abreu (Federal Univ. Rio de Janeiro), Adilson Costa da Silva (Federal Univ. Rio de Janeiro), Alessandro da Cruz Gonçalves (Federal Univ. Rio de Janeiro), Aquilino Senra Martinez (Federal Univ. Rio de Janeiro)

Resonance Treatment of Double-Heterogeneous Fuel Using a Deterministic Statistical Geometry Method in Heterogeneous Transport Calculation Code GALAXY-Z

Kazuya Yamaji (Mitsubishi Heavy Industries), Hiroki Koike (Mitsubishi Heavy Industries), Koji Asano (Mitsubishi Heavy Industries), Satoshi Takeda (Osaka Univ.), Akio Yamamoto (Nagoya Univ.)

Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation

Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Satoshi Takeda (Osaka Univ.), Kazuya Yamaji (Mitsubishi Heavy Industries), Hiroki Koike (Mitsubishi Heavy Industries), Koji Asano (Mitsubishi Heavy Industries)

On the Impact of Fuel Velocity Profile on Loss of Delayed Neutron Precursors in the Molten Salt Reactor Experiment

Mario Ponce Tovar (Seaborg Technologies), Lorenz Fischer (Seaborg Technologies), Lubomir Bures (Seaborg Technologies)

Development of the Molten Salt Reactor Application in French Reference System Code CATHARE3

Ruggero Rosselli (CEA), Nathan Greiner (CEA), Marine Anderhuber (CEA), Théotime Le Borgne de Palfray (CEA)

Development of a Delayed Neutron Precursor Tracking Module for Molten Salt Reactors in the iMC Monte Carlo Code

Inyup Kim (KAIST), Taesuk Oh (KAIST), Yonghee Kim (KAIST)

Quantifying Uncertainties: Evaluating the Impact of Molten Salt Thermal Property Variability on Reactor Operation

Davide Rotilio (Univ. California, Berkeley), Mauricio Tano (INL), Abdalla Abou-Jaoude (INL), Samuel Walker (INL), Massimiliano Fratoni (Univ. California, Berkeley), Renato Gatto (Sapienza Univ. di Roma)

Squirrel; a MOOSE Based App for Solving Quasi-Static Point Kinetics in Molten Salt Reactors

P. Pfahl (Technical Univ. Denmark), A. Chambon (Technical Univ. Denmark), J. Groth-Jensen (Seaborg Technologies), B. Lauritzen (Technical Univ. Denmark)

Verification of a CARIBOU-OpenMC Workflow for the Analysis of HTGR-Like Systems Using the Proposed Ontario Tech Subcritical Assembly

Kevin Sawatzky (Ontario Tech Univ.), Kirk D. Atkinson (Ontario Tech Univ.)

Comparison of Burnup Sensitivity Between Prismatic HTGR and LWR

Go Chiba (Hokkaido Univ.)

Nuclide Inventory Validation: Effect of Nuclear Data Libraries

Germina Ilas (ORNL), Jesse Brown (ORNL)

Simultaneous Adjustment of Uncertain Modeling Parameters and Experimental Data Through Post-Irradiation Examination Data Analyses

Keita Yoshikawa (Hokkaido Univ.), Go Chiba (Hokkaido Univ.), Yuya Inagaki (Hokkaido Univ.), Junshuang Fan (Hokkaido Univ.)

Extension of RMC Burnup Calculations with an Energy-Dependent Branching Ratio Treatment

Hao Luo (Tsinghua Univ.), Jiang Shihang (Tsinghua Univ.), Huang Shanfang (Tsinghua Univ.), Wang Kan (Tsinghua Univ.)

An Iterative RSA-DEM Method for High Packing Fraction Stochastic Media

Zhe Chuan Tan (Singapore Nuclear Research and Safety Initiative), Zhi Yuan Feng (Tsinghua Univ.), Kan Wang (Tsinghua Univ.)

ODR-VS Method for High Packing Fraction of Dispersed Fuel Particles in Annular Container

Zhiyuan Feng (Tsinghua Univ.), Jingang Liang (Tsinghua Univ.), Wenli Guo (Tsinghua Univ.), Kan Wang (Tsinghua Univ.)

Modeling Enhancements and Benchmarking of Pebble Bed Reactors in the Shift Monte Carlo Code

Tarek Ghaddar (ORNL), Friederike Bostelmann (ORNL), Tara Pandya (ORNL), Matthew Jessee (ORNL)

Development of an Equilibrium Modeling Method for Modeling Micro-Modular Pebble-Bed High-Temperature Gas-Cooled Reactors

Annie M. Berens (Univ. Tennessee, Knoxville), Friederike Bostelmann (ORNL), Nicholas R. Brown (Univ. Tennessee, Knoxville)

Investigating the Accuracy of Porous-Medium Treatments in the Analysis of Nuclear Thermal Propulsion Systems

Zach Hughes (TAMU), Carlo Fiorina (TAMU), Nolan MacDonald (Ultra Safe Nuclear), Cristian Garza (Ultra Safe Nuclear), Thomas Guilbaud (École Polytechnique Fédérale de Lausanne), Alessandro Scolaro (École Polytechnique Fédérale de Lausanne)

VERA Solution to the Watts Bar Benchmark Problem

Scott Palmtag (NCSU), Khaldoon Al-Dawood (NCSU), Andrew Godfrey (Veracity Nuclear)

NEA/OECD TVA Watts Bar Unit 1 Multi-Physics Multi-Cycle Depletion Benchmark with CASMO5 and SIMULATE5

Emiliya L. Georgieva (Studsvik Scandpower), Tamer Bahadir (Studsvik Scandpower)

Variability Due to Nuclear Data Applied to the Watts Bar Unit 1 Benchmark with CASMO5/SIMULATE5 Code Sequence

S. Bonthoux (IRSN), J. Taforeau (IRSN)

First Steps of the ANTARES Validation with TVA Watts Bar Unit 1 Cycle 1 Benchmark

F. Bernard (IRSN), S. Bonthoux (IRSN), M. Forestier (IRSN), G. Girault (IRSN), A. Sargeni (IRSN), J. Taforeau (IRSN)

Preliminary Analysis of iDTMC-Assisted Predictor-Corrector Quasi-Static Monte Carlo Simulation in the iMC Code

Taesuk Oh (KAIST), Yonghee Kim (KAIST)

Implementation and Assessment of the Crank-Nicolson Method for the Monte Carlo Multilevel Kinetics Module

Firas Abdullatif (Ohio State), Dean Wang (Ohio State)

A Time-Slicing Method for Capturing Neutron Source Locations for Initializing Dynamic Monte Carlo Simulations

John Tchakerian (MIT), Gavin Ridley (MIT), Timothy Burke (LANL), Benoit Forget (MIT)

Development and Benchmarking of Two Distinct Time-Dependent Random Ray Methods

Maximilian Kraus (Univ. Cambridge), Paul Cosgrove (Univ. Cambridge), Eugene Shwageraus (Univ. Cambridge)

Benchmarking Time Dependent COMET in a Set of Multigroup Kinetic Single Assembly I2S-LWR Problems

Dingkang Zhang (Georgia Tech), Farzad Rahnema (Georgia Tech)

Parallel Simulated Annealing, Genetic Algorithms and Hybrid Method Applied to the Multiobjective Optimization of the Nuclear In-Core Fuel Management

W. Kubinski (Framatome), G. Giorgi (Framatome), M. Segond (Framatome)

Pressurized-Water Reactor Core Design Using Multiobjective Plant Fuel Reload Optimization Platform

Junyung Kim (INL), Mohammad G. Abdo (INL), Congjian Wang (INL), Yong-Joon Choi (INL), Juan Cristhian Luque Gutierrez (NCSU), Jason Hou (NCSU)

Pressurized Water Reactor Gadolinia Pin Location Optimization

Jin Whan Bae (ORNL), Andrew Bielen (U.S. Nuclear Regulatory Commission), Ugur Mertyurek (ORNL), Mehdi Asgari (ORNL)

Optimizerr: A BWR Nuclear Bundle Design Optimizing Tool

Rasmus Renberg (Vattenfall Nuclear Fuel)

Extending MOOSE Capabilities with Discrete and Combinatorial Shape and Topology Optimization for Nuclear Engineering Applications

Muhammad Ramzy Altahhan (NCSU), Sebastian Schunert (INL), Yousry Azmy (NCSU)

MC21/CTF Solutions to OECD/NEA TVA Watts Bar Unit 1 Multiphysics Cycle 1 Benchmark Exercises 1 and 2

Edwin J. Grant (Naval Nuclear Laboratory), Daniel J. Kelly III (Naval Nuclear Laboratory), Brian N. Aviles (Naval Nuclear Laboratory)

MC21/CTF Solutions to OECD/NEA TVA Watts Bar Unit 1 Multiphysics Cycle 1 Benchmark Exercise 3

Edwin J. Grant (Naval Nuclear Laboratory), Daniel J. Kelly III (Naval Nuclear Laboratory), Brian N. Aviles (Naval Nuclear Laboratory)

Development of Serpent -- CTF External Coupling for the OECD/NEA TVA WB1 Benchmark Activities

T. Albagami (NCSU), P. Rouxelin (NCSU), A. Abarca (NCSU), S. Palmtag (NCSU), M. Avramova (NCSU), K. Ivanov (NCSU)

The Random Ray Method Applied to Fixed Source Transport Problems

P. Cosgrove (Univ. Cambridge), J.R. Tramm (ANL)

Application of the Random Ray Method to Global Variance Reduction in Radiation Shielding Problems

V. Raffuzzi (Univ. Cambridge), P. Cosgrove (Univ. Cambridge), P.C. Shriwise (ANL), J.R. Tramm (ANL)

Monte Carlo Calculations in Support of Rod Insertion Measurements

Tanja Goričanec (Jožef Stefan Institute), Luka Snoj (Jožef Stefan Institute), Marjan Kromar (Jožef Stefan Institute)

Applicability of Shift-Generated Albedos for Reactor Analysis with MPACT

Nicholas Herring (Univ. Texas, Austin), Benjamin Collins (Univ. Texas, Austin), Kevin Clarno (Univ. Texas, Austin)

State Estimation and Control in Digital Twins for TRIGA Research Reactors

John Ross (Univ. Texas, Austin), Ben Collins (Univ. Texas, Austin), Kevin Clarno (Univ. Texas, Austin)

Demonstration of Microreactor Reactivity Control with Reinforcement Learning

Majdi I. Radaideh (Univ. Michigan), Dean Price (Univ. Michigan), Kamal Abdulraheem (Univ. Michigan), Moutaz Elias (Lam Research)

Machine Learning Prediction of Pebble History in Pebble Bed Reactors

Ian Kolaja (Univ. California, Berkeley), Tatiana Siaraferas (Univ. California, Berkeley), Yves Robert (Univ. California, Berkeley), Jaewon Lee (Univ. California, Berkeley), Massimiliano Fratoni (Univ. California, Berkeley)

C3-LPO: A Machine Learning Based Surrogate Model for Reactor Design Evaluation and Optimization

Kingsley Ogujiuba (NCSU), Jake Mikouchi-Lopez (NCSU), Gregory Delipei (NCSU), Jason Hou (NCSU)

Generative AI Tools in the Nuclear Engineering Community: A Survey-Based Evaluation of the Current Adoption and Impacts

Oskari Pakari (École Polytechnique Fédérale de Lausanne), Alessandro Scolaro (École Polytechnique Fédérale de Lausanne), Carlo Fiorina (TAMU)

Initial Steps in a Serpent-McStas Two-Way Coupling and its Potential Applications at FRM II

D. Bonete Wiese (Technische Univ. Munchen), C. Hauf (Technische Univ. Munchen), C. Reiter (Technische Univ. Munchen)

Full Core Calculation for FRM II with Serpent 2 and Ansys CFX

Kaltrina Shehu (Forschungs-Neutronenquelle Heinz Maier-Leibnitz), Christian Reiter (Forschungs-Neutronenquelle Heinz Maier-Leibnitz)

Development of High-Fidelity Multi-Physics Platform JAMPAN

Kenichi Tada (Japan Atomic Energy Agency), Ryoichi Kondo (Japan Atomic Energy Agency), Tomohiro Kamiya (Japan Atomic Energy Agency), Taku Nagatake (Japan Atomic Energy Agency), Ayako Ono (Japan Atomic Energy Agency), Yasunobu Nagaya (Japan Atomic Energy Agency), Hiroyuki Yoshida (Japan Atomic Energy Agency)

Recent Advanced Reactor Multiphysics Model Highlights in the Virtual Test Bed (VTB)

Abdalla Abou-Jaoude (INL), Guillaume Giudicelli (INL), Samuel Walker (INL), Emily Shemon (ANL), Hansol Park (ANL), Yiqi Yu (ANL), Nicolas Stauff (ANL)

Validation of ENDF/B-VIII.0 Cross-Section Library for METAL-FAST Graphite Systems

Paul Vollrath (Georgia Tech), Farzad Rahnema (Georgia Tech), Alex Shaw (ORNL)

Investigation of the Impact of TSL Data Libraries and Geometry Variations on the MSRE Benchmark

Aidana Bauyrzhan (NCSU), Ayman I. Hawari (NCSU)

Assessing Criticality Implications of Small Angle Neutron Scattering and Porosity Misrepresentation in ENDF/B-VIII.1 TSLs for Nuclear Graphite

Kemal Ramic (ORNL), Iyad Al-Qasir (ORNL), Friederike Bostelmann (ORNL), Chris W. Chapman (ORNL), Anne Campbell (ORNL), Kyle Grammer (ORNL), Zain Karriem (ORNL), Jose Ignacio Marquez Damian (European Spallation Source), Mark Baird (ORNL), Dorothea Wiarda (ORNL), Luke Daemen (ORNL), Eric Novak (ORNL), Jesse Brown (ORNL), Goran Arbanas (ORNL), Luiz Leal (ORNL), Germina Ilas (ORNL), William A. Wieselquist (ORNL)

Comparison of Coarse Energy Group Structures for Graphite Moderated Molten Salt Reactors and Molten Salt Reactor Experiment Modeling

J. Faulkner (Georgia Tech), B. Petrovic (Georgia Tech)

Reactivity Impact of Updated 35Cl Nuclear Data on the Molten Chloride Reactor Experiment

T. Cisneros (TerraPower), M. Wargon (TerraPower), K. Hanselman (LANL), T. Kawano (LANL), S.A. Kuvin (LANL), H.Y. Lee (LANL)

Hybrid Resolution Approach in Energy and Geometry for Efficient Monte Carlo Coupled Depletion Calculation

Inhyung Kim (Univ. California, Berkeley), Vidor H. Lujan (Georgia Tech), Dan Kotlyar (Georgia Tech), Massimiliano Fratoni (Univ. California, Berkeley)

Verification of Neutronics Analysis Method Using CBZ and GENESIS for a Prismatic High-Temperature Gas-Cooled Reactor

Akio Yamamoto (Nagoya Univ.), Go Chiba (Hokkaido Univ.)

Parametric Analysis of Two-Point Reactors Kinetic Model

Anže Mihelčič (Jožef Stefan Institute), Gašper Žerovnik (Jožef Stefan Institute), Luka Snoj (Jožef Stefan Institute)

Optimization of the Forced Fission Coefficient via Stochastic Calculus

Tamás Zoltan Hajas (Budapest Univ. Technology and Economics), Gabor Tolnai (Budapest Univ. Technology and Economics), Elod Pazman (Budapest Univ. Technology and Economics), David Legrady (Budapest Univ. Technology and Economics)

Computation of HTR-PROTEUS Reaction Rates Ratios C8/F5, F8/F5, and F9/F5 Using MCNP6 with ENDF/B-VIII.0

John D. Bess (JFoster & Assoc.), Oliver Köberl (Axpo Power/Kernenergie)

Preliminary Study on Two-Dimensional SP3 Calculation Based on POD-Local/Global Iterations

Masato Ito (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Yasuhiro Kodama (Nuclear Fuel Industries), Taichi Takeishi (Nuclear Fuel Industries), Hiroaki Nagano (Nuclear Fuel Industries)

Real-Time 3D Fine Spatial Mesh Kinetics Simulator Using POD for Coupled Core

Kaito Ito (Nagoya Univ.), Kosuke Tsujita (Nuclear Engineering), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.)

Neutron Flux Reconstruction from Out-Core Sparse Measurements Using Data-Driven Reduced Order Modelling

Stefano Riva (Politecnico di Milano), Sophie Deanesi (Politecnico di Milano), Carolina Introini (Politecnico di Milano), Stefano Lorenzi (Politecnico di Milano), Antonio Cammi (Politecnico di Milano)

Reconstruction of In-Core Power Distribution Based on POD Using Ex-Core Detector Signals

Yuki Urase (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.)

Hybrid Reduced-Order Modeling Based on Reduced Basis and PCQM Methods for Time-Dependent Diffusion Problem with Cross Section Feedback

Qicang Shen (Univ. Michigan), Brendan Kochunas (Univ. Michigan)

Comparison of Various DNN Modelling Strategies for Assembly Node Averaged Multigroup Cross Section Representation for Nodal Codes

Yi Meng Chan (KTH Royal Institute of Technology), Jan Dufek (KTH Royal Institute of Technology)

An Alternative Approach for Group Constants Regression Based on Supervised Learning Techniques

Lorenzo Loi (Politecnico di Milano), Stefano Riva (Politecnico di Milano), Carolina Introini (Politecnico di Milano), Enrico Padovani (Politecnico di Milano), Francesca Giacobbo (Politecnico di Milano), Antonio Cammi (Politecnico di Milano)

Predicting PWR Fuel Assembly CIPS Susceptibility with Convolutional Neural Networks: Performance and Uncertainty Quantification

Aidan Furlong (NCSU), Farah Alsafadi (NCSU), Scott Palmtag (NCSU), Andrew Godfrey (Veracity Nuclear), Stanley Hayes (Duke Power), Xu Wu (NCSU)

Monte Carlo with Single-Cycle Latency: Optimization of a Continuous Energy Cross Section Lookup Kernel for AI Accelerator Hardware

John Tramm (ANL), Bryce Allen (ANL), Kazutomo Yoshii (ANL), Andrew Siegel (ANL)

Advancements in the Genetic-Driven Optimisation of the Few-Group Structures for Lead Fast Reactors Analysis

A. Aimetta (Politecnico di Torino), N. Abrate (Politecnico di Torino), M. Massone (ENEA), S. Dulla (Politecnico di Torino)

Neutron Shielding Calculation with the ACE-FRENDY-CBZ Sequence

Go Chiba (Hokkaido Univ.)

Multigroup Cross-Section Data Processing for Deterministic Electron-Transport Calculation

Xiaoying Li (Xi’an Jiaotong Univ.), Yunzhao Li (Xi’an Jiaotong Univ.), Ruizhi Shao (Xi’an Jiaotong Univ.), Ning Xu (Xi’an Jiaotong Univ.), Liangzhi Cao (Xi’an Jiaotong Univ.), Tiejun Zu (Xi’an Jiaotong Univ.), Yilin Liang (Xi’an Jiaotong Univ.), Junwei Qin (Xi’an Jiaotong Univ.), Wei Shen (CANDU Owners Group)

Analytic Sensitivity Coefficients for General Multigroup Infinite Medium k-Eigenvalue Problems

Colin A. Weaver (LANL), Michael E. Rising (LANL), Joel A. Kulesza (LANL), Christopher M. Perfetti (Univ. New Mexico), Pablo A. Vaquer (LANL)

Leveraging the Tensor Train Format for Many Energy Groups Deterministic Neutron Transport

Mario I. Ortega (LANL), Duc P. Truong (LANL)

Impact of the Multigroup Velocity Approximation in the Evaluation of the Effective Neutron Lifetime

Giorgio Valocchi (CEA), Jean Tommasi (CEA)

Particle Tracking in Involute-Based Reactor Geometries in SCONE Monte Carlo Code

Mikolaj Adam Kowalski (Univ. Cambridge), Congjin Ding (Univ. Cambridge), Eugene Shwageraus (Univ. Cambridge)

Calculating the Change in Power Shape due to Localised Perturbations to Nuclear Data Using a Generalised Sensitivities Method in MONK

Andrew J. Cox (ANSWERS Software Service), Richard P. Hiles (ANSWERS Software Service), Simon D. Richards (ANSWERS Software Service), Paul N. Smith (ANSWERS Software Service)

Seismic Deformation of Spacer Grids -- Extension of ARCADIA and Validation of Proposed Neutronic Model

J. Marten (Framatome), M. Schneider (Framatome), G. Sieber (Framatome), H. Keßler (Framatome)

UO2-Mo Composite Fuel Model Development and Simulation Using the ENIGMA Code

Aiden Peakman (Univ. Manchester), Glyn Rossiter (National Nuclear Laboratory)

Stability Analyses of the Monte Carlo Neutron Transport with Thermal-Hydraulics Feedback

Kaiwen Li (Tsinghua Univ.), Nan An (Tsinghua Univ.), Hao Luo (Tsinghua Univ.), Jingang Liang (Tsinghua Univ.), Ding She (Tsinghua Univ.), Zhihong Liu (Tsinghua Univ.), Kan Wang (Tsinghua Univ.)

Coarse Mesh Finite Difference Acceleration for Pebble Tracking Transport in Griffin

Yaqi Wang (INL), Joshua Hanophy (INL), Namjae Choi (INL)

Improved Decoupled Diffusion Synthetic Acceleration Scheme for Neutral Particle Transport

Joseph M. Coale (LANL), James S. Warsa (LANL)

Assessing Nonlinear Diffusion Acceleration for Boltzmann Fokker Planck Equation in Slab Geometry

Japan K. Patel (Univ. Michigan), Barry D. Ganapol (Univ. Arizona), Martha M. Matuszak (Univ. Michigan)

An Adaptive Model for Decay Heat Estimation Using Scram Curves

Evgeny Nikitin (Helmholtz-Zentrum Dresden-Rossendorf), Emil Fridman (Helmholtz-Zentrum Dresden-Rossendorf), Alexander Ponomarev (Helmholtz-Zentrum Dresden-Rossendorf)

Pathline Reformulation of the Delayed Neutron Precursors Equation

Mathis Caprais (CEA), Daniele Tomatis (newcleo), Nathan Greiner (CEA), André Bergeron (CEA)

Transport of Highly Volatile Gases Related to Noble Gases and Tritium in the MSRE

Kyoung O. Lee (ORNL), David Kropaczek (ORNL), Jorge Navarro (ORNL)

Nuclear Heating Benchmark in Molten Salt Fast Reactor

A. Chambon (Technical Univ. Denmark), E.P. Senstius (Technical Univ. Denmark), N. Moret (Technical Univ. Denmark)

Benchmarking Between Fuel Cycle Codes and Nuclear Data Evaluations for Decay Heat After a Uranium-233 Fission Pulse

Riko Okuyama (Hokkaido Univ.), Go Chiba (Hokkaido Univ.), Sebastien Lahaye (CEA)

A Numerical Study of the Similarity Between the Decay Heat of PWR and SFR MOX Fuels

D. Da Cunha (CEA), J.-F. Lebrat (CEA), F. Nguyen (CEA), V. Vallet (CEA)

Impact of Inspection Time on Pebble-Bed Reactor Operation

Clément Vayron de la Moureyre (Univ. California, Berkeley), Yves Robert (Univ. California, Berkeley), Massimiliano Fratoni (Univ. California, Berkeley)

ZONER: A Discrete Element Method (DEM) Post-Processing Methodology for Pebble Bed Reactors Spectral Regions Generation

G. Busco (Kairos Power), F. Vitullo (Kairos Power), M. Lee (Kairos Power), J. Herter (Kairos Power), N. Satvat (Kairos Power)

Impact of Coupled DEM and Hyper-Fidelity Depletion on Pebble Bed Burnup

Yves Robert (ORNL), Ludovic Jantzen (Univ. California, Berkeley), Tatiana Siaraferas (Univ. California, Berkeley), Massimiliano Fratoni (Univ. California, Berkeley)

Multiphysics Pebble-Bed Reactor Run-In Simulation Using a High-Fidelity Neutronics--Thermal Hydraulics Framework

R. Stewart (INL), J. Cavaluzzi (INL), P. Balestra (INL), G. Strydom (INL)

Preliminary Study on Multiphysics Transient Calculations for Pebble Bed Reactors Using High-Fidelity Depletion Data

Tatiana Siaraferas (Univ. California, Berkeley), Ludovic V. Jantzen (Univ. California, Berkeley), Yves Robert (ORNL), Faisal A. Alseaidan (Univ. California, Berkeley), Massimiliano Fratoni (Univ. California, Berkeley)

Validation of the NECP-Bamboo Software Based on NPP Measurements

Yilin Liang (Xi’an Jiaotong Univ.), Yunzhao Li (Xi’an Jiaotong Univ.), Yuancheng Zhou (Xi’an Jiaotong Univ.), Yisong Li (Xi’an Jiaotong Univ.), Shilong Zhou (Xi’an Jiaotong Univ.), Hengrui Zhang (Xi’an Jiaotong Univ.), Weiguo Wang (Xi’an Jiaotong Univ.), Yuxiang Ou (Xi’an Jiaotong Univ.), Songzhe Wang (Xi’an Jiaotong Univ.), Junwei Qin (Xi’an Jiaotong Univ.), Ruizhi Shao (Xi’an Jiaotong Univ.), Xiaoying Li (Xi’an Jiaotong Univ.), Wei Shen (Candu Owners Group)

Verification of NECP-Bamboo2.0 with Plate-Fuel-Type Research Reactors

Yunzhao Li (Xi’an Jiaotong Univ.), Junwei Qin (Xi’an Jiaotong Univ.), Fan Xia (Shanghai Nuclear Engineering Research and Design Institute Co.), Hongchun Wu (Xi’an Jiaotong Univ.), Xiaoying Li (Xi’an Jiaotong Univ.), Yilin Liang (Xi’an Jiaotong Univ.), Wei Shen (CANDU Owners Group)

Multi-Physics Sub-Pin Resolution Analysis of a PWR Core with nTRACER/CTF for the OECD/NEA TVA Watts Bar 1 Benchmark

M. Papadionysiou (EPFL), T. Albagami (NCSU), G. Delipei (NCSU), M. Avramova (NCSU), A. Vasiliev (PSI), H. Ferroukhi (PSI), K. Ivanov (NCSU), A. Pautz (PSI)

LDR Lite Benchmark: Description of the Core Model

Riku Tuominen (VTT Technical Research Centre of Finland), Ville Valtavirta (VTT Technical Research Centre of Finland)

Pushing the Envelope for Irradiation Powers and Duration at the Advanced Test Reactor

Nathan Manwaring (INL), Solmayra Flores (INL)

Voronoï Mesh for a Thermally Coupled Model of Pebble Bed Reactor

Ludovic Jantzen (Univ. California, Berkeley), Yves Robert (ORNL), Massimiliano Fratoni (Univ. California, Berkeley)

Deterministic High-Fidelity Neutronics Simulation of Pebble Bed Reactors with Pebble Tracking Transport

Liam Carlson (TAMU), Jean Ragusa (TAMU), Paolo Balestra (INL), Yaqi Wang (INL)

Sensitivity of Thermo-Physical Salt Property Changes on Reactor Equilibrium for Salt-Cooled Pebble Bed Reactors

Ludovic Jantzen (Univ. California, Berkeley), Mauricio E. Tano (INL), Massimiliano Fratoni (Univ. California, Berkeley)

Impact of Cooldown on Pebble Fuel Burnup Prediction Using Machine Learning

Jason Hou (NCSU), Nick Rollins (NCSU)

Assessment of Worth of Telescopic Control Rods in a Pebble Bed Reactor Model

Ethan P. Fowler (Univ. Wisconsin, Madison), Gabriel Paramucchio (Univ. Wisconsin, Madison), Adrien Couet (Univ. Wisconsin, Madison), Peter Wilkinson (Unaffiliated), Ben Lindley (Univ. Wisconsin, Madison)

Development of a Gaseous Fission Products' Model for a Molten Salt Reactor (MSR): Analysis of the Effect of the Gas Removal System's Efficiency on the Concentration of Xenon in the Fuel Circuit

M. Marone (Univ. Grenoble Alpes), P. Rubiolo (Univ. Grenoble Alpes), V. Ghetta (Univ. Grenoble Alpes), J. Giraud (Univ. Grenoble Alpes), F. Quinteros (Univ. Grenoble Alpes)

Griffin's Depletion Calculation of Molten Salt Reactor Experiment

D. Hartanto (ORNL), E. Davidson (ORNL), Y. Cao (ANL), T. Fei (ANL), M. Tano-Retamales (INL)

Effect of Temperature Recirculation on Frequency Response and Stability of Molten Salt Reactors

Lubomir Bures (Seaborg Technologies)

Verification and Validation Activities of Molten Salt Reactors Multiphysics Coupling Schemes at Idaho National Laboratory

Mustafa K. Jaradat (INL), Namjae Choi (INL), Mauricio Tano Retamales (INL), Sebastian Schunert (INL), Abdalla Abou Jaoude (INL), Javier Ortensi (INL)

Modeling the MSRR Using MPACT

Nicholas Herring (Univ. Texas, Austin), Benjamin Collins (Univ. Texas, Austin), Kevin Clarno (Univ. Texas, Austin)

Coupled Simulation of the Sodium Cooled Fast Reactor BN-800 with the GRS System ATHLET-PARCS

J. Bousquet (GRS), Y. Perin (GRS), R. Henry (GRS)

Breakeven Feasibility Study of Chlorine-Based MSFR with Discontinuous and Continuous Fuel Processes

Eunhyug Lee (KAIST), Taesuk Oh (KAIST), Yonghee Kim (KAIST)

New Design Core Options of Micro-Modular Lead Cooled Fast Reactors (MMLFR) for Facilitating Natural Circulation

Seungnam Lee (Hanyang Univ.), Ser Gi Hong (Hanyang Univ.)

Neutronic Benchmark on the Westinghouse Lead Fast Reactor

Nicolas E. Stauff (ANL), Ahmed Abdelhameed (ANL), Alex Levinsky (Westinghouse Electric Co.), Fausto Franceschini (Westinghouse Electric Co.)

Neutronic Analysis of MOX-1000MWth Fast Reactor by Two-Step System Code MCS/RAST-F

Saisundar Mohanty (Ulsan Nat'l Institute Science and Technology), Tran Quoc Tuan (Ulsan Nat'l Institute Science and Technology), Fathurrahman Setiawan (Ulsan Nat'l Institute Science and Technology), Murat Serdar Aygul (Ulsan Nat'l Institute Science and Technology), DeokJung Lee (Ulsan Nat'l Institute Science and Technology)

Towards 2D Reference Deterministic Calculations in Support of Industrial Model Verification and Advanced Reflector Modeling Setup

F. Inzirillo (Politecnico di Milano), A. Brighenti (Framatome), A. Cammi (Politecnico di Milano), L. Graziano (Framatome), A. Hebert (Polytechnique Montréal), G. Marleau (Polytechnique Montréal), S. Santandrea (CEA), B. Vezzoni (Framatome)

New Thermal and Leakage Synthetic Algorithms Applied to Best Estimate Schemes in Lattice Calculations

A. Brighenti (Framatome), S. Santandrea (CEA), L. Graziano (Framatome), B. Vezzoni (Framatome)

Enhancing PWR Monte Carlo Simulations with GREAPMC: A GPU-Accelerated Approach

Muhammad Rizwan Ali (Ulsan Nat'l Institute Science and Technology), Murat Serdar Aygul (Ulsan Nat'l Institute Science and Technology), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)

Enrichment Interpolation for High-Assay Low-Enriched Uranium Fuel Macroscopic Cross Section for Polaris/PARCS

Junsu Kang (Univ. Michigan), Andrew M. Ward (Univ. Michigan), Ugur Mertyurek (ORNL), Thomas J. Downar (Univ. Michigan)

Core Physics Characteristics of Extended Enrichment and Higher Burnup Boiling Water Reactor Fuel

Ugur Mertyurek (ORNL), Riley Cumberland (ORNL), William A. Wieselquist (ORNL)

Comparative Analysis on the Passive Flow Rate Control in the Load-Follow Simulation for Holos-Quad Microreactor

Sooyoung Choi (Univ. Michigan), Qicang Shen (Univ. Michigan), Claudio Filippone (HolosGen), Brendan Kochunas (Univ. Michigan)

Modeling Nuclear Thermal Propulsion Using Nodal Diffusion Codes with Jacobian-Free Newton Krylov Generated Correction Parameters

Jacob Smith (Georgia Tech), Dan Kotlyar (Georgia Tech)

Concept Study of a Fission Fragment Propulsion Nuclear System

Dacai Zhang (Tsinghua Univ.), Xirui Zhang (Tsinghua Univ.), Zhechuan Tan (Tsinghua Univ.), Yuanhao Gou (Tsinghua Univ.), Minzhi Xiong (Tsinghua Univ.), Ganglin Yu (Tsinghua Univ.)

Mass and Power Estimations of Moderated and Unmoderated HALEU Fueled Heat-Pipe Reactors for Space Applications

Riccardo Boccelli (Politecnico di Milano), Marco E. Ricotti (Politecnico di Milano), Angelica Peressotti (Thales Alenia Space Italia), Stefano Lorenzi (Politecnico di Milano), Andrea D'Ottavio (Thales Alenia Space Italia)

A Preliminary Neutronic Analysis of the ALFRED Reactor Core

V. Vitali (newcleo), M. Falabino (newcleo), D. Tomatis (newcleo), M. Carta (newcleo)

Reactor Physics Modelling Challenges of the FLEX Reactor

Simon Boddington (MoltexFLEX), Tom Taylor (MoltexFLEX), Peter Haigh (MoltexFLEX), Eduardo Cuoc (MoltexFLEX), Chris Hankinson (MoltexFLEX), Luke Godfrey (MoltexFLEX)

Updates on the OECD NEA Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)

Oliver Buss (OECD NEA), Hakim Ferroukhi (Paul Scherrer Institute), Kostadin Ivanov (NCSU)

Initial Demonstration of New Griffin Capability for Simulating the Running-In Phase of Pebble-Bed Reactors with Multiphysics

Joshua Hanophy (INL), Javier Ortensi (INL), Paolo Balestra (INL), Yaqi Wang (INL)

Calculation and Analysis of Physical Characteristics of Gaseous Fuel Reactor

Dacai Zhang (Tsinghua Univ.), Wenxiang Fang (Tsinghua Univ.), Zhechuan Tan (Tsinghua Univ.), Minzhi Xiong (Tsinghua Univ.), Yu Ganglin (Tsinghua Univ.)

A Study of Fuel Choice Effects when Transitioning to a Closed Fuel Cycle

S. Richards (ANL), T. Kim (ANL)

3D Full Core Depletion Analysis Using BSOLVE+MCNP6 Analysis of the Washington State University Reactor

Meng-Jen (Vince) Wang (Univ. Nevada, Las Vegas), Glenn E. Sjoden (Univ. Utah), C. Corey Hines (Washington State)

Thermal Analysis of the Sirius-3 Nuclear Propulsion Fuel Experiments

Frederick N. Gleicher (INL), Mustafa K. Jaradat (INL), Sebastian Schunert (INL), Mark DeHart (INL)

Progress on Transport and Transmutation Analysis of Proton Beam Irradiating Long-Lived Spent Nuclear Waste

Charlotte I. Wickert (MIT), Grigor Tukharyan (MIT), Jiankai Yu (MIT), Areg Danagoulian (MIT), Zachary Hartwig (MIT), Benoit Forget (MIT)

Long Time Scale Multiphysics Simulation of Spent Nuclear Fuel Canister in MOOSE

Rodrigo de Oliveira (INL), Joshua Hanophy (INL), Paolo Balestra (INL), Derek Gaston (INL)

Implementation of a Novel ERANOS Procedure for the Adjoint Power Evaluation in Coupled Depletion Problems

Matteo Stanzani (Univ. Bologna), Donato Maurizio Castelluccio (ENEA), Francesco Lodi (ENEA), Vincenzo Giuseppe Peluso (ENEA), Giacomo Grasso (ENEA), Marco Sumini (Univ. Bologna)

Reactivity Decrease by Assembling Fuel Assemblies in a Heavy Water-Cooled Reactor

Tomoatsu Shinohara (Tokyo City Univ.), Naoyuki Takaki (Tokyo City Univ.)

Fuel Cycle Analysis of Wielenga Innovation Static Salt Reactor (WISSR)

Puran Deng (Univ. Michigan), Won Sik Yang (Univ. Michigan), Thomas Wielenga (Wielenga Innovation Foundation)

Multiphysics Analysis of a Minor Actinide Burning Molten Salt Reactor

J. Eickman (Univ. Wisconsin, Madison), M. Nyberg (Univ. Wisconsin, Madison), U. Baker (Univ. Wisconsin, Madison), B. Lindley (Univ. Wisconsin, Madison)

Dynamics and Stability Analysis Study of a Thermal Molten Salt Reactor

Thabit Abuqudaira (TAMU), Ümran Üzen (TAMU), Dahvien Dean (TAMU), Pavel Tsvetkov (TAMU), Piyush Sabharwall (INL)

The LVR-15 Reactor Full Core Analysis in Serpent 2/RINNOVO

Jan Pinta (Research Centre Rez)

On Reactor Neutron Noise Induced by Fuel Assembly Vibrations in Large and Small Heterogeneous Water-Cooled Cores

Salma Magdi Hussein (Chalmers Univ. Technology), Paolo Vinai (Chalmers Univ. Technology), Christophe Demaziere (Chalmers Univ. Technology)

Neutronic Design of a PWR-Based SMR (Small Modular Reactor) Core Using GdN Coating Burnable Absorber for Soluble Boron-Free Operation

Sung Hyun Cho (Hanyang Univ.), Woojin Lee (Hanyang Univ.), Ser Gi Hong (Hanyang Univ.)

ANCKVIPRE Coupled Code Application to PWR Rod Withdrawal from Subcritical Event Analysis

Peter A. Hilton (Westinghouse Electric Co.), Yixing Sung (Westinghouse Electric Co.), Michael Gavalek (Westinghouse Electric Co.), John McMonigal (Westinghouse Electric Co.), Daniel Torres (Westinghouse Electric Co.), Gregory Stehle (Westinghouse Electric Co.)

LDR Lite Benchmark: Coupled 3D Neutronics and Thermal-Hydraulics Analysis of a Control Rod Drop Transient

Rebekka Komu (VTT Technical Research Centre of Finland), Ville Valtavirta (VTT Technical Research Centre of Finland), Riku Tuominen (VTT Technical Research Centre of Finland), Seppo Hillberg (VTT Technical Research Centre of Finland)

The Preliminary Assessment of the Feasibility of Transporting a Spent Microreactor from Shielding Perspective

T. Fei (ANL), M. Atz (ANL)

Modeling Approaches for Depletion of a TRISO-Fueled Microreactor

Keenan J. Hoffman (LANL), Alexis Maldonado (LANL), Todd S. Palmer (Oregon State)

Global Core Environment Effects on Multigroup Cross Sections for Finer Energy Structures Within Microreactors

Aaron Sommer (Georgia Tech), Farzad Rahnema (Georgia Tech), Abderrafi M. Ougouag (Georgia Tech), Dingkang Zhang (Georgia Tech), Mark DeHart (Georgia Tech)

Exploring Effects of Homogenization on an OpenMC Depletion Analysis of a TRISO Fueled, Helium Cooled Microreactor

Lewis I. Gross (Univ. Wisconsin, Madison), Patrick Shriwise (ANL), Benjamin Lindley (Univ. Wisconsin, Madison), Paul P.H. Wilson (Univ. Wisconsin, Madison)

Loading Pattern Optimization for LWRs Using Monte Carlo Tree Search

Rikuto Kasama (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.)

Scalarized Multiobjective Fuel Loading Optimization of Extended-Cycle NuScale Power Module with Evolutionary Algorithms

Thomas Jayasankar (Univ. Michigan), Dean Price (Univ. Michigan), Majdi I. Radaideh (Univ. Michigan), Brendan Kochunas (Univ. Michigan)

Learning Nuclear Fuel Management, Case Study: Design of a Two-Year Equilibrium Cycle of a BWRX-300-like Small Modular Reactor

Arturo Jiménez-Facio (Univ. Nacional Autónoma de México), Juan-Luis Francois (Univ. Nacional Autónoma de México)

Stochastic Optimization to Find Reference Core Configuration for Refueling Simulations of Waste-Burning Stable Salt Reactor

Seungug Jae (Univ. Michigan), Won Sik Yang (Univ. Michigan), Thanh Hua (ANL), Yan Cao (ANL), Tom Taylor (Moltex Energy), Luke Godfrey (Moltex Energy)

First Results of Uranium Nitride Fuel Characterization Using Accelerated Fuel Qualification Process

A. Levinsky (LANL), Z. Miller (LANL), M. Fratoni (Univ. California, Berkeley), T. Matthews (LANL), G.T. Craven (LANL), M.W.D. Cooper (LANL), V. Mehta (LANL), D.A. Andersson (LANL), J.T. Rizk (LANL)

Mobile Small Reactor Minor-Actinide Proliferation Resistant Fuel in LEU+ Once-Through Operation Cycle Performance Verification

Gray S. Chang (JFoster & Assoc.), John D. Bess (JFoster & Assoc.), Patrick Moo (JFoster & Assoc.), Julie Foster (JFoster & Assoc.)

Progress Toward the Development of a High-Fidelity Neutronic Model of MARVEL Using Griffin

S. Terlizzi (INL), I. Trivedi (INL)

Steady-State and Transient Analysis of a Heat-Pipe Cooled Micro-Reactor Using the DireWolf Code Suite

Tatiana Siaraferas (Univ. California, Berkeley), Vefa Kucukboyaci (Westinghouse Electric Co.), Mykola Boychenko (Westinghouse Electric Co.), Massimiliano Fratoni (Univ. California, Berkeley)

Modeling of a Representative MHTGR 350MWth Supercell with RAPTOR

Luke Wells (Georgia Tech), Andrew Johnson (Ultra Safe Nuclear), Dan Kotlyar (Georgia Tech)