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2018 SCALE Users' Group Workshop

Event Contacts

Brad Rearden, 865-574-6085;

Germina Ilas, 865-241-4672;

Will Wieselquist, 865-574-0204;



Monday, August 27, 2018








Emerging Initiatives in SCALE

Brad Rearden, ORNL

SCALE Capabilities to Support NRC Licensing Review

Don Algama, US Nuclear Regulatory Commission

NRC Advanced Reactor Licensing Activities

George Flanagan, ORNL

Mutually Beneficial Developments in SCALE+CASL

Kevin Clarno, ORNL

SCALE Support by the DOE/NNSA Nuclear Criticality Safety Program

Doug Bowen, ORNL


Working Lunch Talk

GAIN: What is it and is it helping?

Andy Worrall, ORNL







Advanced Reactor Modeling with SCALE


Developments and Application of SCALE for MSR Analysis Modeling with TRITON

Ben Betzler, ORNL

High-Fidelity MSR Modeling with VERA-MSR

Ben Collins, ORNL

Confirmatory Analysis of NuScale’s Reactor Physics Design with Polaris/PARCS/PATHS

Andrew Bielen, US Nuclear Regulatory Commission

Assessment of SCALE Capabilities for HTR Modeling and Simulation

Friederike Bostelmann, ORNL

The AMPX/SCALE Capability with the AMPX 1597-g Library for Advanced Reactor Analysis

Kang Seog Kim, ORNL



Applications of SCALE to Nuclear Safeguards and Security


Uncertainty Analysis with SCALE/Sampler for Neutron Active Interrogation Calculations

Matt Jessee, ORNL

3D Visualization in Fulcrum

Rob Lefebvre, ORNL

Use of ORIGEN for Safeguards Application of the PROSPECT Antineutrino Experiment

Andrew Conant, Georgia Tech

Use of ORIGAMI/ORIGEN for Spent Fuel Safeguards

Jianwei Hu, ORNL



Tuesday, August 28, 2018




LWR Modeling with SCALE


TRITON/Shift Depletion Validation

Brian Ade, ORNL

SCALE-PARCS Pin Power Uncertainty for Watts Bar

HZP & Hatch Gamma Detector Modeling with Polaris-PARCS

Andrew Ward, University of Michigan

Advanced BWR Criticality Safety with Quantified Uncertainty Using Various SCALE Modules

Dean Price, University of Illinois

Using the Fission Source Mesh Tally to Validate KENO for Pin Power

Justin Clarity, ORNL



Decommissioning, Disposal, and Spent Nuclear Fuel Burnup Credit


A Summary of the Recent BWR BUC Project at ORNL

BJ Marshall, ORNL

Validation of SCALE for BWR SNF

Ugur Mertyurek, ORNL

Detailed SCALE Dose Rate Evaluations for a Consolidated Interim Spent Nuclear Fuel Storage Facility

Georgeta Radulescu, ORNL

UNF-ST&DARDS: A Unique Tool for Spent Nuclear Fuel Characterization Using SCALE

Kaushik Banerjee, ORNL


Working Lunch Talk

Nuclear Data and Benchmarking Program

Brad Rearden, ORNL



Reactor Safety Analysis with SCALE


Reactor Safety Analysis with SCALE

Matthias Behler, GRS

Neutronic and Thermal-Hydraulic Feasibility Studies for HFIR Conversion to LEU U3Si2-Al Fuel

David Chandler, ORNL

ENDF/B-VIII.0 Testing with AMPX, SCALE, and VALID

Andrew Holcomb, ORNL

NCSU Activities on High Temperature Reactor Design Using SCALE

Paolo Balestra, NCSU

Nodal Data Generation

Will Wieselquist, SCALE Director, ORNL



Applications of SCALE for Nuclear Criticality Safety Practitioners


Criticality Convergence Confusion

Dale Lancaster,

Applications of SCALE for H-Canyon at the Savannah River Site

Joshua Butler, SRNS

Analytical Geometry and Enriched Uranium Solutions in SCALE: Two H-Canyon Studies

Tracy Stover, SRNS

The Use of SCALE in the Licensing and Inspection of NRC-Regulated Fuel Cycle Facilities

Jeremy Munson, US Nuclear Regulatory Commission

Epithermal/Intermediate Spectrum Critical Experiment Using SPR/CS

Justin Clarity, ORNL



Wednesday, August 29, 2018




Integration of SCALE Capabilities for Multiphysics Analysis


Secondary Neutron Source Modeling with SCALE and VERA

Andrew Godfrey, ORNL

SCALE/FAST Coupling Status

Will Wieselquist, SCALE Director, ORNL

Integration of Thermochimica with ORIGEN Using the ORIGEN-API

Bernard Fitzpatrick, UOIT



Validation, Verification, and Uncertainty Quantification


New SCALE Capability for Uncertainty Quantification of the Kinetic Parameters

Majdi Radaideh, University of Illinois

Preliminary SCALE Results for the OECD/NEA Benchmark for Uncertainty Analysis in Modeling of SFRs

Friederike Bostelmann, ORNL

ENDF/B-VIII Covariance Libraries

Vlad Sobes, ORNL

Critical Experiment Correlations

BJ Marshall, ORNL

Criticality Validation of SCALE 6.2

Ellen Saylor, ORNL



ORIGEN Activation Analysis of the Sile Experiment

Sampler Applied to Source Term Uncertainty

Using ORIGAMI for Detailed Spent Fuel Assembly Analysis in Safeguards Applications

Introduction to the Polaris Lattice Physics Code

MAVRIC Cask Analysis with ORIGEN Spent Fuel Sources

Linking External C++ or Fortran Software to the ORIGEN API

KENO-VI Modeling of Double Heterogeneous Reactor Systems Using TRISO Fuel

Generation of SCALE Multi-Group Fast Reactor Libraries with AMPX

Click HERE to see the photos from the 2018 SCALE Users' Group Workshop.