2018 SCALE Users' Group Workshop

Event Contacts

Brad Rearden, 865-574-6085; reardenb@ornl.gov

Germina Ilas, 865-241-4672; ilasg@ornl.gov

Will Wieselquist, 865-574-0204; wieselquiswa@ornl.gov

Topic

Speaker

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

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

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

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

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

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

Criticality Convergence Confusion

Dale Lancaster, NuclearConsultants.com

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

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

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