*** Please note that because this is a limited release distribution, approval from the developer is required prior to final RSICC approval. ***
1. NAME AND TITLE
STANDARDS 6.0.0 : Storage Transportation and Disposal Analysis Resource and Data System.
RESTRICTIONS:
STANDARDS 6.0.0 is restricted to individuals from federal government organizations responsible for managing or regulating used nuclear fuel (UNF), their contractors, or the regulated commercial nuclear power industry. Organizations expected to benefit from the use of STANDARDS include the U.S. Department of Energy and its contractors; the U.S. Nuclear Regulatory Commission (NRC) and its contractors; U.S. NRC Certificate of Compliance (CoC) holders for UNF storage or transportation packages; U.S. commercial nuclear power generating utilities; Independent Spent Fuel Storage Installations (ISFSIs); or equivalent foreign organizations engaged in cooperation with the United States Government and its national laboratories regarding the safe long-term management of UNF. Federal regulations may restrict the distribution of the STANDARDS code.
2. CONTRIBUTOR
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
Pacific Northwest National Laboratory, Richland, Washington.
3. CODING LANGUAGE AND COMPUTER
Java, Python; Windows (C00873PCX8602).
4. NATURE OF PROBLEM SOLVED
To understand the changing nuclear and mechanical characteristics of SNF and the storage, transportation, and disposal systems at various stages within the waste management system, several types of analyses are required. These analyses require the use of assorted tools and numerous data types. Using the appropriate modeling and simulation (M&S) parameters and the diversity of analytic tools needed to conduct SNF analyses can be a tedious, error-prone, and time-consuming undertaking for analysts and reviewers alike.
5. METHOD OF SOLUTION
STANDARDS is an integrated data and analysis system designed to simplify and automate the performance of accurate and efficient evaluations for characterizing the input to the overall waste management system. A relational database has been assembled to provide a standard means by which STANDARDS can succinctly store and retrieve M&S parameters for specific SNF analysis. SNF data can be imported into this database for user-specific analysis. A library of analysis model templates provides the ability to communicate the various sets of M&S parameters to the most appropriate M&S application. A process manager facilitates performance of actual, as-loaded, assembly-specific, and cask-specific evaluations. Interactive visualization capabilities facilitate data analysis and results interpretation.
STANDARDS 6.0.0 includes the following capabilities:
An UNF database (relational database tables) for storing and preserving UNF data and supplying data to various UNF analyses
Various graphical user interface (GUI) based data importers for importing user-specific data to the STANDARDS database
Automated assembly-specific depletion and decay analyses using the SCALE nuclear code
Canister-specific criticality, misload, and shielding analyses using the SCALE nuclear code
Canister-specific thermal analysis using COBRA-SFS thermal hydraulic code,
Design basis decay, criticality, thermal, shielding, and site boundary analyses using user-defined, design basis assembly and loading configurations
Detailed decay and criticality analyses using detailed irradiation history
Various sensitivity analyses for defining bounding and design basis configurations for dry storage systems
GUI-based data interrogation
Sample reactor (SCALE-ORIGEN) libraries for selected PWR and BWR fuel types, and
Sample criticality (SCALE-KENO), shielding (SCALE-MAVRIC), and thermal (COBRA-SFS) templates
Canister loading optimization analysis
SCALE 6.3.2 or later and COBRA-SFS 6.3.0 or later licenses are required for running any analysis using STANDARDS. Users are required to import their data for assembly-specific and canister-specific analyses..
6. RESTRICTIONS OR LIMITATIONS
None noted.
7. TYPICAL RUNNING TIME
Problem dependent.
8. COMPUTER HARDWARE REQUIREMENTS
Windows.
9. COMPUTER SOFTWARE REQUIREMENTS
Java, Python.
10. REFERENCES
a) Included in documentation:
User Documentation for STANDARDS 6.0 (September 30, 2026).
Nuclear Technology Journal, Volume 199, Issue 3 (September 2017).
11. CONTENTS OF CODE PACKAGE
The package is distributed via web downloadable links; it contains the referenced document in PDF format and compressed zip Windows executable files, sample problems, data, and reference material.
12. DATE OF ABSTRACT
September 2026
13. KEYWORDS: DATABASE, SPENT FUEL