Accessible Data Files in SCALE and How to Use Them: II.JSON and CSV
SCALE 6.3 provides users of ORIGEN with several new ways to represent and interrogate data. In this tutorial, users will learn about three new formats for exporting ORIGEN data and how to access them using the OBIWAN command-line tool. For nuclide inventories, these include comma-separated value (CSV) format and the new JSON-based “Inventory Interface” format (II.JSON). For ORIGEN reactor libraries, this consists of the open HDF5 standard. Tutorial attendees will learn how to render ORIGEN data in these formats and how they can be used by tools like Python for follow-on analysis. No prior experience with SCALE is required, although familiarity with ORIGEN and the command line is helpful. Attendees can follow along using SCALE 6.3.
Activation Analysis with ORIGEN/MAVRIC for Advanced Reactors
This tutorial will demonstrate the application of ORIGEN and MAVRIC for activation analysis for an advanced reactor concept. ORIGEN will be used to generate the activation source terms and MAVRIC will be employed to calculate dose rates due to activated materials. No prior experience with SCALE is required. Attendees can follow along using SCALE 6.3.
Decay Heat and Source Terms Analysis with SCALE
This tutorial will walk users through different approaches and relevant files for decay heat and neutron and gamma source terms calculation for LWR spent fuel, using fuel depletion and decay capabilities in SCALE. Attendees will learn how to: determine decay heat and neutron and gamma sources and spectra based on fast simulations with ORIGEN under the ORIGAMI graphical user interface; use F71 files obtained with different SCALE depletion sequences as input for standalone ORIGEN simulations to determine decay heat or neutron and gamma sources as function of burnup and cooling time, and visualize the results with Fulcrum. A hands-on example looking at the impact of modeling assumptions (0D vs 1D) for an LWR fuel assembly on the SCALE-predicted decay heat and radiation sources will be provided. No prior experience with SCALE is required. Attendees can follow along using SCALE 6.3.
Frequent Fulcrum Functions: The Basics of SCALE’s Graphical User Interface
This tutorial will introduce the Fulcrum graphical user interface and the basic functions that enhance the common activities of creating, editing, navigating, executing, and visualizing SCALE input files. This tutorial will help attendees become familiar with the Fulcrum input file text editor and the integrated input development environment features of autocompletion, automatic checking, cursor context, and input navigation. In addition, the Fulcrum and SCALE runtime environment will be reviewed to improve understanding of job execution workflow. No prior experience with SCALE is required. Attendees can follow along using SCALE 6.3.
Fulcrum Data and Geometry Visualization
This tutorial will review the data plotting and geometry visualization capabilities in the Fulcrum graphical user interface. Attendees will become familiar with Fulcrum’s 2D and 3D geometry visualization features. Attendees will learn how to identify plottable data items, compose and export plot and plot data for SCALE plot formats (SDF, Ampx MG/CE, PLT, F71, PTP, SPF, ORIGEN gamma data, etc.) and visualize, navigate, cut, hide, and export the geometry and spatial data (fission map, dose map, etc.) overlays in 2D and 3D. No prior experience with SCALE is required. Attendees can follow along using SCALE 6.3.
MAVRIC: Long-Distance Statistics for Activation
This tutorial will demonstrate how to use MAVRIC and ORIGEN to activate a common operational component, a pump, for a nuclear reactor and calculate dose rates for a radiation worker due to activated component. First, MAVRIC will be used to estimate the neutron flux due to nuclear fission in the reactor core by utilizing CADIS method to optimize the flux tally at the pump. ORIGEN will be used to create a gamma source due to activated pump. Finally, MAVRIC will be used again to estimate dose rates around the pump by importing the activation source generated by ORIGEN. No prior experience with SCALE is required. Attendees can follow along using SCALE 6.3.
Modeling of TRISO fuel with SCALE
This tutorial will demonstrate SCALE 6.3 capabilities for reactor physics and fuel inventory analyses of pebble-bed reactors such as high temperature gas-cooled reactors. This will use the TRITON reactor physics sequence to leverage new geometry input options for detailed continuous-energy models as well as established input options for fast multi-group models. The tutorial will include the development and testing of a computational model and the postprocessing of results for purposes of fuel inventory interrogation. No prior experience with SCALE is required. Attendees can follow along using SCALE 6.3.
Molten Salt Reactor Analysis with SCALE
This tutorial will demonstrate SCALE 6.3 capabilities for reactor physics and fuel cycle analyses of liquid-fueled systems, such as molten salt reactors. This will use the TRITON module and leverage new input definitions to define elements being fed into and removed from an irradiated mixture. The tutorial will include the development and testing of a computational model, verification activities for complex material flow scenarios, and postprocessing to perform fuel cycle analyses. Resolving additional short-time phenomena will be briefly discussed. No prior experience with SCALE is required. Attendees can follow along using SCALE 6.3.
Nuclear data UQ for HALEU/HBU LWR fuel using Sampler
This tutorial will introduce the application of the Sampler sequence to perform uncertainty analysis for high-assay low-enriched uranium (HALEU)/high burnup (HBU) and accident tolerant fuel (ATF) concepts. Participants will learn how to use Sampler features to identify similarities and differences in decay heat and nuclide inventory trends for light water reactor (LWR) fuel. No prior experience with SCALE is required. Attendees can follow along using SCALE 6.3.
ORIGEN Reactor Library Generation with Polaris
This tutorial will guide users through the process of generating ORIGEN reactor libraries using Polaris and applying these libraries for rapid depletion calculations with ORIGEN or ORIGAMI. This will consist of a basic overview of developing a LWR assembly template using Polaris and then using the new Python-based ORIGEN Library Manager (OLM) tool to define a complete interpolation grid of fuel assembly configurations, generate input permutations, execute inputs, assemble the results in a complete ORIGEN reactor data library, and perform quality testing on the resulting library. Attendees may follow using SCALE 6.3. Prior experience with SCALE (particularly familiarity with ORIGEN and/or ORIGAMI) is highly recommended.
Sampler for Nuclear Criticality Safety Applications
This tutorial will provide examples of using features of the Sampler uncertainty quantification tool to nuclear criticality safety applications. The users will learn how to develop and execute parametric investigations and apply perturbations of geometry or material parameters, as well as of other variables of interest. Attendees can follow along using SCALE 6.3.
SCALE Utilities for Nuclear Data Interrogation, Comparison, and Visualization
This tutorial is an introduction to the tools available to interrogate, compare, and visualize the SCALE nuclear data. We will use Fulcrum to plot continuous energy and multigroup cross section data, multigroup scattering matrices, covariance matrices, and correlation matrices. We will also demonstrate how to use Fulcrum to compare cross section and uncertainty data from different evaluated nuclear data releases. Users will get the chance to use the OBIWAN tool to view/patch/diff/convert data found on F33 and F71 files. Lastly, a variety of AMPX tools will be used to compare covariance libraries, compare working and master libraries, and print/manipulate the data stored on a multigroup library. No prior experience with SCALE is required. Attendees can follow along using SCALE 6.3.
Sensitivity Analysis Capability in ORIGEN
This tutorial will introduce users to the new sensitivity feature in ORIGEN, which enables the exploration of the impact of nuclear data changes on responses of interest. It will demonstrate through simple exercises that are representative of real-life applications the power of this feature in supporting a deeper understanding of the underlying physics. Attendees can follow along using SCALE 6.3.
Similarity Assessment for Nuclear Criticality Safety
This tutorial will provide a high-level overview on the workflow for similarity assessments using SCALE. Users will be provided example cases and pre-generated sensitivity data files to use to follow along through a step-by-step demonstration similarity assessment. Attendees can follow along using SCALE 6.3.
VADER for Criticality Safety Validation
This tutorial will demonstrate criticality safety validation exercises using the VADER sequence in SCALE 6.3.1. This tutorial will use VADER under the Fulcrum user interface to develop upper subcritical limits (USLs) for hypothetical criticality safety applications based on critical experiment data. Several statistical tests and USL determination methods will be demonstrated. No prior experience with SCALE is needed for this tutorial. Attendees can follow along using SCALE 6.3.