RSICC CODE PACKAGE PSR-446
1. NAME AND TITLE
FUELS DATA: Code System to Model Verification Fuel Rod Data.
Idaho National Engineering Laboratory, Idaho Falls, Idaho, through the Energy Science and Technology Software Center, Oak Ridge, Tennessee.
3. CODING LANGUAGE AND COMPUTER
FORTRAN IV; CDC CYBER 175 (P00446C760000).
4. NATURE OF PROBLEM SOLVED
FUELS DATA is a collection of machine-readable fuel behavior data from domestic and foreign water reactor test facilities developed for use in model verification of the Nuclear Regulatory Commission FRAP codes. The FUELS DATA package contains an editing program to read and print a formatted listing of the fuels data file containing measured data and design parameters developed for model verification for the FRAPCON and FRAP-T programs.
5. METHOD OF SOLUTION
Measurements have been formatted and stored to facilitate computer application. The storage format for each fuel rod entry provides identification data, design parameters, power history, and corresponding measurement history. The verification data base is expanded prior to evaluating each new version of the model to enable verification runs to have continuing independent benchmark significance. The storage structure is made up of 11 separate file types, 10 of these corresponding to different card types and associated card formats. The identification and design block includes the first four card types: 1, 2, and 3 appear for each entry. 1 provides the rod designation and run number and experiment and reference report designation. 2 contains data availability flags for the 15 measurement parameters which follow and specifies the number of measurement locations. 3 represents the main design, fabrication, and system condition data. If local measurements are available, 4 gives the instrument location. 5 and 6 describe the rod operating history. 5 specifies the heat rating and cumulative irradiation time at the end of an operating step and the associated step power and burnup condition measurements. 6 describes normalized axial power distributions during different operating history periods. The rod measurement history is defined by card types 7 through 11. 7 and 8 contain instrumented rod measurements corresponding to operating steps defined by card type 5. 9 and 10 contain integral measurements related to gas, void, pressure, and axial deformation conditions. 11 represents PIE measurements for melt radius, corrosion thickness, permanent hoop strain, and gap conductance from grain growth determination.
6. RESTRICTIONS OR LIMITATIONS
Maxima of - 70 operating steps, 5 axial power distribution profiles. FUELS DATA contains only steady-state fuel behavior data.
7. TYPICAL RUNNING TIME
A formatted listing of the fuels data file can be produced using the editing program in about 20 CP seconds on a CDC CYBER176 and 9 CP seconds on a CDC CYBER175. Approximately 6.5 CP seconds are required for a typical categorical processing run on a CDC CYBER176 and 17 CP seconds on a CDC CYBER175.
8. COMPUTER HARDWARE REQUIREMENTS
37,000 (octal) words of memory are used by the auxiliary editing program on a CDC CYBER175; 44,000 (octal) words of memory are required on a CDC CYBER176.
9. COMPUTER SOFTWARE REQUIREMENTS
The code ran under NOS/BE 1.4 and requires a Fortran IV compiler. The FUELS DATA code was tested at NESC in 1984 and was not retested or modified when transferred to RSICC and released in March 2001.
N.L. Hampton, "INEL Fuel Code Assessment Data Base Access and Description," EGG-NTAP-6056, Revision 1 (March 1983).
N. L. Hampton, "INEL Fuel Code Assessment Data Bank Description and Users Manual," EGG-CAAD-5486 (July 1981).
R. Chambers, N.L. Hampton, and E.T. Laats, "Fuel Code Assessment Data Sample Report," EGG-CAAP-5114 (February 1980).
"FUELS DATA NESC No. 844.C176C," NESC Note 84-40 (June 25, 1984).
11. CONTENTS OF CODE PACKAGE
Included are the referenced documents and one DS/HD diskette which includes the Fortran source, fuel rod behavior data file and test case input in a self-extracting compressed DOS file.
12. DATE OF ABSTRACT
KEYWORDS: HEAT TRANSFER; REACTOR SAFETY