2017 SCALE Users' Group Workshop

Topic:

Nuclear Science and Technology

Event Contacts	Brad Rearden, 865-574-6085; reardenb@ornl.gov
	Germina Ilas, 865-241-4672; ilasg@ornl.gov
	Matt Jessee, 865-241-1503; jesseema@ornl.gov

Tuesday, September 26, 2017

Plenary Session Session Chair(s): Brad Rearden & Germina Ilas
Topic	Speaker
Introduction to the SCALE Code System	Brad Rearden, Manager, SCALE Code System, ORNL
SCALE and the NRC: Past, Present, and Future	Drew Barto, Nuclear Regulatory Commission
Balancing the SCALE for 30 Years	Larry Wetzel, BWXT
Fulcrum User Interface Highlights	Rob Lefebvre, ORNL
Accuracy and Runtime Improvements in SCALE 6.2	Matt Jessee, ORNL
Uncertainty in Anything: The Future with SCALE/Sampler	Will Wieselquist, ORNL
CyBORG: Employing the ORIGEN API in a Fuel Cycle Simulator	Steve Skutnik, University of Tennessee
Shielding Capabilities in SCALE 6.2	Douglas Peplow, ORNL
NRC Shielding Analysis for Spent Fuel Transportation and Storage	Michel Call, Nuclear Regulatory Commission
The REGAL Programme: Technical Details & SCALE Assessment	Kevin Govers, SCK-CEN, Belgium
Sensitivity to Nuclear Data in a Lead-Cooled Fast Reactor	Fred Adams, CNL, Canada

Wednesday, September 27, 2017

Criticality Safety Session Chair: Doug Bowen
Presentation Title	Speaker
Only the Best Models are in VALID	B. J. Marshall, ORNL
Criticality Safety Validation of SCALE 6.2	B. J. Marshall, ORNL
BWR Burnup Credit	Brian Ade, ORNL
An Overview of New Monte Carlo Capabilities in SCALE	Greg Davidson, ORNL
Shift Verification and Validation Efforts	Tara Pandya, ORNL
Depletion Applications for Commercial Spent Nuclear Fuel	Dale Lancaster, NuclearConsultants.com

Depletion and Source Terms Session Chair: William Wieselquist
Presentation Title	Speaker
Overview of Changes to the ORIGEN Family of Codes from 6.1 to 6.2	Will Wieselquist, ORNL
Using ORGEN to Help Probe Gamma-Ray Burst Mysteries	Robert Hayes, North Carolina State University
Examples of SCALE Uses at Studsvik Sweden	Jitka Zakova, Studsvik Nuclear AB, Sweden
COUPLE/ORIGEN Cross Section Generation for Reactor Physics Applications	Josh Peterson-Droogh, ORNL
High-Fidelity Modeling of Spent Fuel Assemblies for Advanced NDA Instrument Testing	Jianwei Hu, ORNL
Decay Heat Uncertainty due to Modeling and Nuclear Data Uncertainties	Germina Ilas, ORNL

Nuclear Data Session Chair: Cihangir Celik
Presentation Title	Speaker
Multigroup Data Libraries for SCALE Applications	Mark Williams, ORNL
Introduction to AMPX	Doro Wiarda, ORNL
SCALE Multi-Group Libraries for Sodium-Cooled Fast Reactors	Friederike Bostelmann, Germany (Presenter: Brad Rearden, ORNL)
How to Generate Your Own Covariance Library	Doro Wiarda, ORNL
Getting Started with SCALE - Installation and Updates	Rob Lefebvre, ORNL

Working Lunch Panel Moderator: Brad Rearden, ORNL, Manager, SCALE Code System, 2009 - Present
Presentation Title	Speaker
The Heritage of the SCALE Code System	Mike Westfall, ORNL (ret.), Originator of SCALE, 1976
	Lester Petrie, ORNL (ret.) - Principal developer and architect of SCALE, 1976-2016
	Cecil Parks, ORNL - SCALE Project Leader, 1979-1994
	Steve Bowman, ORNL - SCALE Project Leader, 1995-2009

Radiation Shielding Session Chair: Douglas Peplow
Presentation Title	Speaker
SCALE Criticality and Shielding Analysis using UNF-ST&NDARDS	Kaushik Banerjee, ORNL
SCALE Input Preparation Using Template Engine	Henrik Liljenfeldt, ORNL
MAVRIC/Monaco Neutron Activation Simulations with Critical Sources	Thomas Miller, ORNL
Experience in Using MAVRIC for Shielding Analysis at the Nuclear Safety Council	Jorge Peña Gutiérrez, Consejo de Seguridad Nuclear, Spain
MAVRIC Shielding Analyses of SNF Transportation and Dry Storage Casks	Georgeta Radulescu, ORNL
Using SCALE for Radiation Transport Simulations to Determine Radiation Environment in I2S-LWR	Tim Flaspoehler, Georgia Tech

Reactor Physics Session Chair: Steve Bowman
Presentation Title	Speaker
SCALE 6.2 Reactor Physics Capabilities	Matthew Jessee, ORNL
Overview of GENPMAXS/PARCS Capabilities Utilizing SCALE Cross Sections	Andy Ward, University of Michigan
Recent Progress in Validating POLARIS for US NRC Use	Peter Yarsky, NRC
Are SCALE Lattice Codes Perfect Enough?	Ugur Mertyurek, ORNL
SCALE Lattice Physics Applications to 3D Nodal Diffusion Simulations with NESTLE	Ivan Maldonado, University of Tennessee
Molten Salt Reactor Neutronics Tools in SCALE	Jeff Powers, ORNL

Sensitivity and Uncertainty Analysis Session Chair: Mark Williams
Presentation Title	Speaker
SCALE 6.2 TSUNAMI Overview	Chris Perfetti, ORNL
Evaluation of ENDF/B-VIII Covariance Data	B.J. Marshall, ORNL
Optimizing HFIR Isotope Production Through a Sensitivity-Informed Target Design Process	Susan Hogle, ORNL
Converting SCALE Cross Section Files to NEMTAB Format for Full-Core Nodal Diffusion Uncertainty Analysis	Alvaro Bernal Garcia, Universitat Politécnica València, Spain
Application of Sampler to the UAM Benchmark	Will Wieselquist, ORNL
Implementation of Resonance Parameter Sensitivity Coefficients Calculation in CE TSUNAMI-3D	Vlad Sobes, ORNL
Uncertainty Analysis on LWR and HTGR Core Modeling Using SCALE Tools	Jason Hou, North Carolina State University

Tutorial Sessions

ORIGAMI Spent Fuel Characterization

TSUNAMI Sensitivity/Uncertainty Analysis

Polaris Lattice Physics Calculations

Sampler Uncertainty Quantification

Click HERE to see the photos from the 2017 SCALE Users' Group Workshop.