Advances in Nuclear Fuel Management (ANFM 2025)

Full Issue

Analysis of Fuel Safety Issues in Boron-Free SMRs through Full-Core Simulation: Mitigation through Integrated Core Design and Fuel Analysis

Chansoo Lee (Seoul National University), Kyuseok Shim (Seoul National University), Jooil Yoon (KEPCO International Nuclear Graduate School), Hui-Jeong Jeong (KAERI), Youho Lee (Seoul National University)

Economic Performance of a Low Power Density PWR-style SMR

F. Ferella (Uppsala Univ.), M. Seidl (Westinghouse Electric Co.), F. Franceschini (Westinghouse Mangiarotti), A. Solders (Uppsala Univ.), C. Gustavsson (Uppsala Univ.), H. Sjostrand (Uppsala Univ.), U. Bergmann (Westinghouse Electric Co.), J. Kierkegaard (Westinghouse Electric Co.)

Fine Group Structure Optimization for Pebble Bed Reactor Simulations

Andrew P. Panter (Univ. Michigan, Ann Arbor), Hansol Park (ANL), Changho Lee (ANL), Brendan Kochunas (Univ. Michigan, Ann Arbor)

Sensitivity Study of 𝐾eff to Neutron Cross-Section Perturbations in a Sodium-Cooled Fast Reactor Using MOX and Metal Fuels

Oyeon Kum (KIRAMS)

A Breed-and-Burn Strategy Proposal for Mizton, a Heat Pipe-Cooled Microreactor

Emiliano Morones-García (UNAM), Juan-Luis François (UNAM)

SCALE Modeling and Inventory Generation for a Generic TRISO-Fueled Heat Pipe Micro Reactor

Donny Hartanto (ORNL), Friederike Bostelmann (ORNL), Georgeta Radulescu (ORNL), Tarek Ghaddar (ORNL), Rabab Elzohery (ORNL), William Wieselquist (ORNL)

MARIE: A Python-Based Framework for Comprehensive Fuel Recycling Modeling

Steve E. Skutnik (ORNL), Randy Ngelale (ORNL), Laura Arias Chavez (ORNL), Robert A. Lefebvre (ORNL), Jin Whan Bae (ORNL), Brianna Hiscox (ORNL), Leigh Martin (ORNL), Andrew Worrall (ORNL)

MOX and UOx Fuel Multi Recycling in Pressurized Water Reactors

Hervé Billat (EDF), Enrico Girardi (EDF R&D), Francois-Xavier de Cordoue (EDF), Loic Pussard (EDF), Guillaume Vaast (EDF), Badiaa Amekraz (Framatome)

Selective Conversion of Transuranic Oxides to Species Soluble in Molten Chloride Salt - Validation of the First Stage of the WATSS Recycling Process

J. P. Zuniga (Moltex Energy), I. Scott (Moltex Energy), O. Gregoire (Moltex Energy), A. D. Warren (Moltex Energy), R. Brown (Moltex Energy), G. Cota-Sanchez (Canadian Nuclear Laboratory), L. Bradford (Canadian Nuclear Laboratory), D. Cluff (Canadian Nuclear Laboratory), K. Kovack (Canadian Nuclear Laboratory), D. Poff (Canadian Nuclear Laboratory), R. O'Sullivan (Moltex Energy)

Modeling a Thermal-Spectrum LEU-fueled Molten Salt Reactor Co-fueled with Thorium in SCALE 6.3.1 and Serpent-2

C. Erika Moss (Univ. Tennessee, Knoxville), Ondrej Chvala (Univ. Tennessee, Knoxville), Donny Hartanto (ORNL), John P. Carter (INL)

Sensitivity of RPT Homogenization of Double-Heterogeneous Fuels to Reactor Characteristics Variation

Nicholas F. Herring (Veracity Nuclear), Benjamin S. Collins (Veracity Nuclear)

Implementation of a Fuel-Cladding Chemical Interaction Model for Metallic U-Zr and U-Pu-Zr Fuels for Sodium-Cooled Fast Reactors in FAST

Dylan Wray (PNNL), Ken Geelhood (PNNL), Kevin Clarno (Univ. Texas, Austin)

Analysis of Plutonium and Minor Actinides Generation in Pebble Bed Modular Reactors

G. Alonso (ININ), R. C. Lopez (ININ), E. Martinez (ININ)

Deep Learning Application for Thermal Limit Bias Predictions in BWRs

Jeremy Barnhart (Constellation), Anirudh Tunga (Blue Wave AI Labs), Jonathan Nistor (Blue Wave AI Labs), James Tusar (Constellation)

Use of Machine Learning to Address Moisture Carryover (MCO) in Boiling Water Reactors

Victoria Micallef (Constellation), Sanchari Banerjee (Blue Wave AI Labs), Jonathan Nistor (Blue Wave AI Labs), James Tusar (Constellation)

Spacer Relocation Signature for GNF3 Fuel Assemblies with Raised Water Rods

Jonathan Nistor (Blue Wave AI Labs), Baris Sarikaya (Constellation), James Tusar (Constellation), Michael Mueterthies (Blue Wave AI Labs)

Improving Core Observables with Entropy-Based Debiasing Inference Methodology

Atul Karve (Global Nuclear Fuel), Ayden Cohn (GE Hitachi), Roger Doles (Global Nuclear Fuel), Hany Abdel-Khalik (Purdue Univ.)

Thermal Limit Modeling for Core Design in Boiling Water Reactors Using Deterministic and Machine Learning Approaches

M. Rizki Oktavian (Blue Wave AI Labs), Michael J. Mueterthies (Blue Wave AI Labs), Charles Karlson (Blue Wave AI Labs), Maria Berardi (Blue Wave AI Labs), Anirudh Tunga (Blue Wave AI Labs), Phil McCalley (Blue Wave AI Labs), Jordan Heim (Blue Wave AI Labs), Antti Kankkunen (Blue Wave AI Labs), J. Thomas Gruenwald (Blue Wave AI Labs), Jonathan Nistor (Blue Wave AI Labs)

Design of Boiling Water Reactor Equilibrium Cycles using Genetic Algorithms with PARCS and Neural Network Surrogates

Michael J. Mueterthies (Blue Wave AI Labs), M. Rizki Oktavian (Blue Wave AI Labs), Maria Berardi (Blue Wave AI Labs), Charles Karlson (Blue Wave AI Labs), Nathanael Hudson (U.S. Nuclear Regulatory Commission), Peter Yarsky (U.S. Nuclear Regulatory Commission), Nazila Tehrani (U.S. Nuclear Regulatory Commission), Randall Dunavant (Southern Nuclear Co.), Aaron Phillippe (Southern Nuclear Co.), Ashley Thompson (Southern Nuclear Co.), Phil McCalley (Blue Wave AI Labs), Anirudh Tunga (Blue Wave AI Labs), Jordan Heim (Blue Wave AI Labs), Antti Kankkunen (Blue Wave AI Labs), J. Thomas Gruenwald (Blue Wave AI Labs), Jonathan Nistor (Blue Wave AI Labs)

Investigation on Dimension Reduction Techniques for Visualization of Reactor Core Design Space

Juan C. Luque-Gutierrez (NCSU), Jake Mikouchi-Lopez (NCSU), Jason Hou (NCSU)

Development of CIPS Prediction Model of Nuclear Reactor Core Operation by Applying ViT and Encoder-Decoder

Dongmin Yun (Ulsan Nat'l Institute Science and Technology), Sang-Rae Moon (KHNP-CRI), Sung Jin Jeong (Pusan Nat'l Univ.), Hyun Chul Lee (Pusan Nat'l Univ.), Jihun Kim (BotBot Inc.), Ji Woo Lee (Universal Co.), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)

The CONCORS Software Method for Coupled Code Simulation

Matthew Adler (Studsvik), Jeffrey Borkowski (Studsvik), Lotfi Belblidia (Studsvik)

Recent Developments and Applications of the SOSA Shuffling Sequence Code

P. H. Wakker (NRG PALLAS), M. P. Brinkman (NRG PALLAS), H. P. M. Gibcus (NRG PALLAS)

Extension of the In-Core Shuffling Algorithm to PWRs in MARLA

Dave Knott (Studsvik), Christian Oyarzun (Studsvik), Tung D.C. Nguyen (Studsvik), Jeffrey Borkowski (Studsvik)

Novel Evolutionary Algorithm for Solution of Multicycle Core and Fuel Design Optimization

David Kropaczek (Veracity Nuclear), Benjamin Collins (Veracity Nuclear), Aaron Graham (Veracity Nuclear), Andrew Godfrey (Veracity Nuclear)

Reinforcement Learning for BWR Core-Level Fuel Management

Loukas Carayannopoulos (MIT), Michael Holmes (Constellation), Nicholas Szewczyk (Constellation), Kathryn Biegel (Constellation), James Tusar (Constellation), Koroush Shirvan (MIT)

Review of the InCore Nuclear Fuel Management over the Operating Life of a PWR NPP

Juan Antonio Bermejo (CNAT), Alberto Ortego (CNAT), Juan Carlos Martines-Murillo (CNAT)

Multi-Cycle Core Design Optimization with Multiple Input and Output Constraints

Aaron M. Graham (Veracity Nuclear), Benjamin S. Collins (Veracity Nuclear), David Kropaczek (Veracity Nuclear)

Design Methods to Reduce Risk of Crud-Induced Power Shift in Pressurized Water Reactors Case Study

Alexandra R. Dixon (Duke Energy)

Optimizing Boiling Water Reactor Fuel Cycle Economics under Steam Dryer Performance Constraints with the aid of a Machine-Learning based Moisture Carryover Predictive Tool

Aaron Phillippe (Southern Nuclear Co.), Jackie Golabek (Southern Nuclear Co.), Randy Dunavant (Southern Nuclear Co.), Johnathan Nistor (Blue Wave AI Labs), Sanchari Banerjee (Blue Wave AI Labs)

Extended Fuel Cycle Optimization of a Generic B&W PWR Using Gadolinia Burnable Poison Only

Zachary D. Bevans (NCSU), Scott P. Palmtag (NCSU)

COPERNICUS -- Optimization Code for PWR Design and Analysis

Tung D.C. Nguyen (Studsvik), Dave Knott (Studsvik), Christian Oyarzun (Studsvik), Jeffrey Borkowski (Studsvik)

FARGO - Integrated Lattice and Loading Pattern Optimization, Overview and Example Application

G. Hobson (Framatome)

ROSA-BWR: Optimization Software for Boiling Water Reactor In-Core Fuel Management

Matteo Gamarino (NRG PALLAS), Pieter H. Wakker (NRG PALLAS)

Best-Estimate Enhanced Option III - A Non-parametric Statistical Analysis of BWR Stability Events

C. Myers (Framatome), D. Tinkler (Framatome)

Validation of Axpo's SIMULATE-3K Models against Stability Measurements of Leibstadt Nuclear Power Plant

A. Dokhane (Axpo), A. Noel (Axpo), G. Malavasi (Axpo), S. Baumgartner (Axpo), D. Chionis (Axpo)

Westinghouse Extended Operating Domain Stability (WEOD-S) Solution

Camilla S. Rotander (Westinghouse Electric Sweden)

Olkiluoto 3 EPR Cycle 1 Core Physics Tests and Flux Maps Evaluation with SIMULATE5

J. Kumpula (TVO), V. Hynönen (TVO), T. Lamminpää (TVO), L. Rintala (TVO), M. I. K. Santala (TVO), M. Dahlfors (TVO)

Analyzes of Startup Physics Tests in Sanmen Nuclear Power Plant

Shi Jianfeng (SNERDI), Fei Jingran (SNERDI), Yang Bo (SNERDI), Bi Guangwen (SNERDI), Du Chao (CNPO), Qian Zhongyou (Sanmen Nuclear Power Co.), Li Ang (CNPO)

Watts Bar Unit 2 Cycle 1 Predictions using PARAGON2/ANC Code System

James N. Laird (Westinghouse Electric Co.), Hudson Watkins (Westinghouse Electric Co.)

Applicability of MHI Nuclear Design Code System GalaxyCosmo-S® for PWR Core Analysis After Long Shutdown Periods

Hiroki Koike (Mitsubishi Heavy Industries), Kazuya Yamaji (Mitsubishi Heavy Industries), Kosuke Hiramatsu (Mitsubishi Heavy Industries), Masato Yamamoto (Mitsubishi Heavy Industries), Koji Asano (Mitsubishi Heavy Industries), Daisuke Sato (Mitsubishi Heavy Industries)

High-Burnup BWR LOCA Burst Analysis Framework Development

Ian Greenquist (ORNL), Nathan Capps (ORNL), Mehdi Asgari (ORNL), Aaron Wysocki (ORNL), Shane Henderson (ORNL), Robert Salko Jr. (ORNL), Baris Sarikaya (Constellation), James Tusar (Constellation), Ian Porter (GE Vernova Inc)

Neutronic Performance Analysis of 60 MWe Small Modular Reactor Core with LEU+ Fuels and GdN Coating Burnable Absorbers

Seung Hyeon Choi (Hanyang Univ.), Ser Gi Hong (Hanyang Univ.)

Cycle Optimization for a 4-loop PWR Using Multicycle Constraint Annealing

Zachary D. Bevans (NCSU), Aidan Furlong (NCSU), Scott P. Palmtag (NCSU)

Neutronic Analysis for Accident Tolerant Fuel and Control Rod Loaded APR- 1400 with STREAM/RAST-K 2.0 code

Eun Jeong (Ulsan Nat'l Institute Science and Technology), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)

PWR Reload Core Design and Licensing Strategies for HALEU and High Burnup

Bradley Balltrip (Southern Nuclear Co.), Matthew Leonard (Westinghouse Electric Co.), Radu Pomirleanu (Westinghouse Electric Co.)

Improved Instrumentation Analytics for GNF Core Monitoring System

Xavier Mouney (Global Nuclear Fuel), Roger Doles (Global Nuclear Fuel), Atul Karve (Global Nuclear Fuel)

ARGOS Core Follow and Prediction Features - Nuclear Operator Experiences

L. Ackermann (Framatome), S. Merk (Framatome)

Application of Mitsubishi Core Monitoring System VISION for Core Management of Japanese PWR Plants

Kosuke Hiramatsu (Mitsubishi Heavy Industries), Hiroki Koike (Mitsubishi Heavy Industries), Masafumi Matsui (Mitsubishi Heavy Industries), Yohei Kamiyama (Mitsubishi Heavy Industries), Yusuke Himuro (Mitsubishi Heavy Industries), Koji Asano (Mitsubishi Heavy Industries)

Safety Analysis Technical Considerations for Achieving PWR Cycle Extensions: Part I

Tom Kindred (Southern Nuclear), Sam Lafountain (Southern Nuclear), Tim Collart (Southern Nuclear), Kevin Barber (Westinghouse Electric Co.)

Simple Models for Predicting the Feed Assembly Need and Assembly Burnup in Boiling Water Reactors

Rasmus Renberg (Vattenfall Nuclear Fuel), Erik Dalborg (Vattenfall Nuclear Fuel)

Low Enrichment 2-Year Fuel Cycle to Mitigate MCO

Shea McCarthy (Constellation), James Tusar (Constellation), Stephanie Alford (Constellation), Dale Bradish (Constellation)

AP1000 PWR Simulations using PARAGON2/ANC Code System

Baxter G. Durham (Westinghouse Electric Co.), Terry L. Signorella (Westinghouse Electric Co.), Ho Q. Lam (Westinghouse Electric Co.), Kevin Pierce (Westinghouse Electric Co.), Adrianna Kwiecien (Westinghouse Electric Co.), Jason Behrens (Southern Nuclear Co.), Dang Ho (Southern Nuclear Co.)

Comparison of CMS5 Predictions to KONVOI Neutron Flux Map Measurements

Emiliya L. Georgieva (Studsvik), Marcus Seidl (PreussenElektra), Tamer Bahadir (Studsvik)

SIMULATE5-K Coupling Interface to Thermal-Hydraulics System Codes

Matthew Adler (Studsvik), Gerardo Grandi (Studsvik), Tamer Bahadir (Studsvik), Jeffrey Borkowski (Studsvik)

Startup Tests of Barakah Nuclear Power Plant: Measurements vs. Predictions

Eissa Alkindi (ENEC), Rashed Al Maqdahi (ENEC)

Python-based Reload Optimization Framework for SIMULATE-3 and Mlrose

James W. Carnal (Univ. Tennessee, Knoxville), Noah M. Marks (Univ. Tennessee, Knoxville), G. Ivan Maldonado (Univ. Tennessee, Knoxville)

Core Design Optimization of a Soluble-Boron-Free Small Modular Pressurized Water Reactor with ROSA

Henk P. M. Gibcus (NRG PALLAS), Bright M. Mweetwa (Bangor Univ.), Matteo Gamarino (NRG PALLAS), Frank C. M. Verhagen (NRG PALLAS), Pieter H. Wakker (NRG PALLAS), Marat Margulis (Univ. Derby)

A Parametric Study of Genetic Algorithm using IPWR Core Design

Jake Mikouchi-Lopez (NCSU), Jaun C. Luque-Gutierrez (NCSU), Mitch Edney (NCSU), Jason Hou (NCSU)

Implementation of Fuel Management Capabilities for Multi-cycle Optimization in RAVEN

Juan C. Luque-Gutierrez (NCSU), Junyung Kim (INL), Congjian Wang (INL), Nicholas Rollins (NCSU), Svetlana Lawrence (INL), Mohammad G. Abdo (INL), Jason Hou (NCSU)

Fuel Assembly Lattice Designs using High Enrichment and Hybrid Burnable Absorbers - Zirconium Diboride and Gadolinia

Damon Bryson (Duke Energy)

BISON Modeling of ZIRLO Cladding for Reactivity Initiated Accident Separate Effects

Landry D. Wells (Univ. Tennessee, Knoxville), Nicholas R. Brown (Univ. Tennessee, Knoxville)

A Soluble Boron-Free Core Design Having Cr-coated GdN-CBA for Load-Following Operation with Two Control Rod Designs

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

Evaluation of Framatome Shielding Fuel Assemblies in the Swedish Nuclear Power Plant Ringhals 3

L. Ackermann (Framatome), C. Möllmer (Framatome), J. Peucker (Framatome)

Pin Placement Optimization for Single and Dual Gadolinia Loading Patterns in Pressurized Water Reactor Fuel Assemblies

Danielle Harris (Duke Energy)

Peacock: A Monte Carlo Transport Code with Depletion for Reactor Modeling

William C. Dawn (Studsvik), Charles Wemple (Studsvik)

Studsvik's Core Management System 5: Overview and Recent Developments

R. Ferrer (Studsvik), J. Hykes (Studsvik), T. Bahadir (Studsvik), G. Grandi (Studsvik), T. Simeonov (Studsvik), J. Rhodes III (Studsvik)

Sensitivity Study of Epithermal Resonance Up-scattering Using the SCALE/Polaris-PARCS Code Procedure for LWR Physics Analysis

Kang-Seog Kim (ORNL), William A. Wieselquist (ORNL)

A Low-memory Eigenvalue Sensitivity Calculation Method for Deterministic Neutron Transport

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

SCALE 6.3 Enhancements to the Polaris Lattice Physics Code for Light-Water Reactor Confirmatory Analysis

Matthew A. Jessee (ORNL), Ugur Mertyurek (ORNL), Kang Seong Kim (ORNL), Shane W. D. Hart (ORNL), Andrew M. Holcomb (ORNL), Jin Whan Bae (ORNL), Byoung Kyu Jeon (ORNL), William A. Wieselquist (ORNL)

A Whole-Core Multiphysics Microreactor Simulator

Aaron M. Graham (Veracity Nuclear), Micah Best (Veracity Nuclear), Benjamin S. Collins (Veracity Nuclear), David Kropaczek (Veracity Nuclear), Andrew Godfrey (Veracity Nuclear)

Development Status of STREAM3D-GPU: a GPU-enabled Neutron Transport Code for Large PWR Simulation

Siarhei Dzianisau (Ulsan Nat'l Institute Science and Technology), Fathurrahman Setiawan (Ulsan Nat'l Institute Science and Technology), Hyungwoo Sohn (Ulsan Nat'l Institute Science and Technology), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)

Recent Advances in MPACT for TRISO-fueled Microreactor Analysis

Sooyoung Choi (Univ. Michigan), Brendan Kochunas (Univ. Michigan, Ann Arbor), Vefa Kucukboyaci (Westinghouse Electric Co.)

Whole Core Reactor High Fidelity Calculations using the RAPID Code System

Brian Stroh (Virginia Tech), Alireza Haghighat (Virginia Tech)

Verification of CMS5 for Higher Enrichment and High Burnup PWR Core Design

Rodolfo Ferrer (Studsvik), William C. Dawn (Studsvik), Tamer Bahadir (Studsvik)

Validation of CMS5 against Otto Hahn Critical Experiment Benchmark

Tamer Bahadir (Studsvik), Rodolfo M. Ferrer (Studsvik)

Evaluation of GNF's Advanced Core Simulator Performance for Modern BWR Core Designs

Virinder Sandhu (Global Nuclear Fuel), John Hannah (Global Nuclear Fuel), Belgacem Hizoum (Global Nuclear Fuel), Brandon LaFleur (Global Nuclear Fuel), Yuxuan Liu (GE Hitachi), Leonid Pogosbekyan (Global Nuclear Fuel), Anthony Reese (Global Nuclear Fuel)

Benchmarking CASMO5 against Monte Carlo for PWR Lattices with Higher U-235 Enrichments

Joshua Hykes (Studsvik), Rodolfo Ferrer (Studsvik)

CASMO5 Analysis of Kurchatov Critical Experiments with 7.5-10% Enrichment

Joshua Hykes (Studsvik), Rodolfo Ferrer (Studsvik)

Functional Expansion Tallies for Kinetic Monte Carlo Variance Reduction

Martin Skretteberg (Univ. Cambridge), Paul Cosgrove (Univ. Cambridge), Mikolaj A. Kowalski (Univ. Cambridge)

VERA-Enabled Monte Carlo Solutions for the Watts Bar Benchmark Problem

Andrew Godfrey (Veracity Nuclear), Benjamin Collins (Veracity Nuclear)

VERA-Enabled High-Fidelity Excore Transport Applications with Shift

Andrew Godfrey (Veracity Nuclear), Benjamin Collins (Veracity Nuclear)

The ENDF/B Nuclear Data Library and its Impact on Reactor Simulations

Gustavo P.A. Nobre (Brookhaven), David A. Brown (Brookhaven)

GNF's BWR Core Tracking Observations with Recent ENDF/B and JENDL Releases

Yuxuan Liu (GE Hitachi), John Hannah (Global Nuclear Fuel), Virinder Sandhu (Global Nuclear Fuel), Abigail Davis (Global Nuclear Fuel), Leonid Pogosbekyan (Global Nuclear Fuel)

Nuclear Data Usage at Studsvik Scandpower and Future Needs from ENDF/B-IX

C. A. Wemple (Studsvik), R. M. Ferrer (Studsvik), T. T. Simeonov (Studsvik), J. M. Hykes (Studsvik), W. C. Dawn (Studsvik), J. D. Rhodes (Studsvik)

Comparison of ENDF/B Libraries for Sodium Fast Reactor Models

Abigail Davis (GE Hitachi Nuclear Energy), Jacob Bartel (GE Hitachi Nuclear Energy), Zhiwen Xu (Terrapower)

Benchmark of SIMULATE5-K Against Frigg Loop Experiments

Gerardo Grandi (Studsvik)

Improvement of the Cross-Section Reconstruction Model in PWR Core Calculation Code

Kento Yamamoto (Nuclear Fuel Industries, Ltd.), Yasuhiro Kodama (Nuclear Fuel Industries, Ltd.), Koji Ito (Nuclear Fuel Industries, Ltd.), Hideaki Hyoudou (Nuclear Fuel Industries, Ltd.), Go Chiba (Hokkaido Univ.), Yuya Inagaki (Hokkaido Univ.)

Verification of Nodal Transient Code SIMULATE5-K against the NEACRP Control Rod Ejection Accident Benchmark

P. Mala (Studsvik), T. Bahadir (Studsvik), G. M. Grandi (Studsvik)

Progression Problems for the Verification of Optimization Code Performance

David Kropaczek (Veracity Nuclear), Benjamin Collins (Veracity Nuclear), Aaron Graham (Veracity Nuclear), Andrew Godfrey (Veracity Nuclear)

Simulating Challenging BWR Operation Conditions with CMS5

Petri Forslund Guimarães (Studsvik), Tamer Bahadir (Studsvik), Christian Jönsson (Studsvik), Joshua Hykes (Studsvik), Rodolfo Ferrer (Studsvik)

BWR Control Blade Depletion Modeling with SIMULATE5

Tamer Bahadir (Studsvik)

Acceleration of 3D Nodal Diffusion Code RAST-K for Transient Analysis using Memory Access Pattern Optimization and Parallelization

Hyungwoo Sohn (Ulsan Nat'l Institute Science and Technology), Jinsu Park (Ulsan Nat'l Institute Science and Technology), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)

APEX: An Efficient and Fast-Running Simulator for Multicycle Core Analysis

David Kropaczek (Veracity Nuclear), Andrew Godfrey (Veracity Nuclear), Benjamin Collins (Veracity Nuclear), Aaron Graham (Veracity Nuclear)

CIPS Index Predictions for Fixed Incore Detection Systems

Benjamin S. Collins (Veracity Nuclear), Cole Gentry (Veracity Nuclear), Andrew Godfrey (Veracity Nuclear), Dave J. Kropaczek (Veracity Nuclear)