RSICC Home Page RSICC COMPUTER CODE CCC-873
*** 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 5.0 : Storage Transportation and Disposal Analysis Resource and Data System.
STANDARDS 5.0 is restricted to individuals from federal government organizations responsible for managing or regulating spent nuclear fuel (SNF), 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 SNF 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 SNF. Federal regulations may restrict the distribution of the STANDARDS code.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
Pacific Northwest National Laboratory, Richland, Washington.
3. CODING LANGUAGE AND COMPUTER
Java, Python; Windows (C00873PCX8600).
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 5.0 includes the following capabilities:
· An SNF database (relational database tables) for storing and preserving SNF data and supplying data to various SNF 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
· GUI-based analysis template development
· 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
· Spent Nuclear Fuel Inventory Projection
SCALE 6.2 or later and COBRA-SFS 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
7. TYPICAL RUNNING TIME
8. COMPUTER HARDWARE REQUIREMENTS
9. COMPUTER SOFTWARE REQUIREMENTS
a) Included in documentation:
User Documentation for STANDARDS 5.0 (August 2023).
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
13. KEYWORDS: DATABASE, SPENT FUEL