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*** Please note, this is a limited release distribution, approval from the developer is required prior to final RSICC approval. ***

 

1.   NAME AND TITLE

UNF-ST&DARDS 4.1.sp1:  Used Nuclear Fuel – Storage, Transportation & Disposal Analysis Resource and Data System.

RESTRICTIONS:

UNF-ST&DARDS 4.1.sp1 is restricted to individuals from federal government organizations responsible for managing or regulating used or spent nuclear fuel (SNF), their contractors, or the regulated commercial nuclear power industry. Organizations expected to benefit from the use of UNF-ST&DARDS 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 UNF-ST&DARDS code.

 

2.   CONTRIBUTOR

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

 

3.   CODING LANGUAGE AND COMPUTER

Java, Python; Windows (C00848PCX8602).

 

4.   NATURE OF PROBLEM SOLVED

To understand the changing nuclear and mechanical characteristics of spent or used nuclear fuel (SNF or UNF) and the different storage, transportation, and disposal systems at various stages within the waste management system, different types of analyses are required. These types of analyses require the use of assorted tools and numerous types of data. Using the appropriate modeling and simulation (M&S) parameters and 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

A new, integrated data and analysis system has been designed to simplify and automate the performance of accurate and efficient evaluations for characterizing the input to the overall waste management system—UNF-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS). A relational database has been assembled to provide a standard means by which UNF-ST&DARDS can succinctly store and retrieve M&S parameters for specific SNF analysis. Users can import SNF data into this database for user-specific analysis. A library of various analysis model templates provides the ability to communicate the various set 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.

 

UNF-ST&DARDS Version 4.1.sp1 capabilities include:

·                     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 UNF-ST&DARDS database,

·                     Automated assembly-specific depletion and decay analyses using SCALE nuclear code,

·                     Canister-specific criticality, misload, and shielding analyses using 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/design-basis configurations for dry storage systems,

·                     GUI-based data interrogation capability,

·                     GUI-based analysis template development capability,

·                     Sample reactor (ORIGEN) libraries for selected PWR and BWR fuel types, and

·                     Sample criticality (KENO), shielding (MAVRIC), and thermal (COBRA-SFS) templates

·                     Canister loading optimization analysis

·                     Spent Nulear Fuel Inventory Projection

 

 

SCALE 6.2 or later and COBRA-SFS licenses are required for running any analysis using UNF-ST&DARDS. 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. 

 

10.  REFERENCES

a) Included in documentation:

            User Documentation for UNF-ST&DARDS 4.1.sp1 (April 2021).

            Nuclear Technology Journal, Volume 199, Issue 3 (September, 2017).

 

11.  CONTENTS OF CODE PACKAGE

The package is distributed on 2 DVDs which contains the referenced document in PDF format and a compressed zip files Windows executable files, Sample problems, data and reference material.

 

12.  DATE OF ABSTRACT

      April 2021

 

13.  KEYWORDS:  DATABASE, SPENT FUEL