2019 SCALE Users' Group Workshop

Topic:

Nuclear Science and Technology

Event Contacts	Brad Rearden
	Germina Ilas, 865-241-4672, ilasg@ornl.gov
	Will Wieselquist, 865-574-0204, wieselquiswa@ornl.gov

Monday, August 19, 2019

PLENARY SESSION
Topic	Speaker
Emerging Initiatives in SCALE	Will Wieselquist, ORNL
NRC's Advanced Reactor Program	John Monninger, US Nuclear Regulatory Commission
Introduction of the SCALE Team	Will Wieselquist, ORNL
A Decade of CASL Impact and Future Direction	Dave Kropaczek, ORNL
Transformational Challenge Reactor: Nuclear Core Design with Advanced Manufacturing	Ben Betzler, ORNL

Working Lunch Talk GAIN: What is it and is it helping?	Andy Worrall, ORNL

TECHNICAL SESSIONS

Advanced Reactor Modeling with SCALE:
Nodal Data Calculation in TRITON/Shift: Part 1, Applications	Matt Jessee, ORNL
Nodal Data Calculation in TRITON/Shift: Part II, Tally Methods	Will Wieselquist, ORNL
Molten Salt Reactor Fuel Cycle and Reactor Physics Analysis with SCALE/TRITON	Ben Betzler, ORNL
SCALE Multigroup Capability and Challenges in Advanced Reactor Analysis	Kang Seog Kim, ORNL
Generation of ORIGEN Reactor Libraries for Liquid Fueled Molten Salt Reactor Designs	Kyle Anderson, University of Tennessee

Applications of SCALE to Nuclear Safeguards and Security
Monte Carlo Uncertainty Quantification in UF6 Neutron Emissions	Ryan O'Mara, North Carolina State University
Retrospective assay of UF6 to Discriminate Historical HEU from LEU	Robert Hayes, North Carolina State University
INDEPTH Demonstration	Brandon Grogan, ORNL
Kernel Density Estimators for Sampler Analysis	Ryan O'Mara, North Carolina State University

Tuesday, August 20, 2019

Reactor Safety Analysis with SCALE
MELCOR/SCALE for HTGRs	Will Wieselquist, ORNL
Polaris/PARCS Full Core Assessment	Ugur Mertyurek, ORNL
NCSU's RDFMG Ongoing Activities with SCALE	Pascal Rouxelin, North Carolina State University
Polaris Updates in SCALE 6.3	Matt Jessee, ORNL

Applications of SCALE for Nuclear Criticality Safety
CSAS/Shift Integration within SCALE 6.3	Kursat Bekar, ORNL
User Experiences with the ICSBEP Distributed SDFs with SCALE - 2019 Edition	Justin Clarity, ORNL
Initial KENO Validation with ENDF/B-VIII Nuclear Data in SCALE 6.3.0-beta4	B.J. Marshall, ORNL
Preliminary TSUNAMI Assessment of the Impact of Accident Tolerant Fuel Concepts on Reactor Physics Validation	B.J. Marshall, ORNL

Working Lunch Talk Nuclear Data Activities for Nuclear Energy Applications	Brad Rearden, ORNL

Nuclear Data for SCALE Applications
Sampler Sensitivity Indices	Friederike Bostelmann, ORNL
Updates on ORIGEN Readers and Data	Shane Hart, ORNL
Augmented Covariance Data Libraries for SCALE 6.3	Vlad Sobes, ORNL
Developing 3D Reactor Model for Criticality Safety Analysis of the Newly Converted NIRR-1 using the KENO-VI Module of the SCALE Code System	Abjulhameed Salawu, Federal University Lokoja

Decommissioning, Disposal, and Spent Nuclear Fuel Burnup Credit
Detailed Radiation Dose Rate Evaluations of Commercial Spent Nuclear Fuel Canisters	Georgeta Radulescu, ORNL
Artificial Neural Network for MOX Criticality Prediction using SCALE/TRITON	Jin Whan Bae, ORNL
Comparison of MPACT and Shift for MAGNOX Reactors	Brian Ade, ORNL

TUTORIALS

Activation Analysis of the Silene Experiment with ORIGEN/MAVRIC

Criticality Analysis with CSAS/Shift and 3D Visualization in Fulcrum

Optimization and Uncertainty Quantification for Criticality Safety with Sampler

SCALE Utilities for Nuclear Data Interrogation, Comparison, and Visualization

Nodal Data Generation for Core Simulators with TRITON/Shift

Generation of SCALE Multi-Group Libraries with AMPX

Research Reactor Source Terms with ORIGEN for Safeguards Applications

Time-Dependent Depletion Analysis with Polaris

Click HERE to see the photos from the 2019 SCALE Users' Group Workshop.