RSICC DATA PACKAGE DLC-201

1. NAME AND TITLE OF DATA LIBRARY

PWR-AXBUPRO-SNL: Axial Burnup Profile Database for Pressurized Water Reactors.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

None included.

3. CONTRIBUTORS

Yankee Atomic Electric Company, Bolton, Massachusetts, through the OECD Nuclear Energy Agency Data Bank, Issy-Les Molineaux, France.

4. HISTORICAL BACKGROUND AND INFORMATION

The data were obtained directly from utilities whose reactors represent the range of commercial PWR fuel lattices. The work was performed by Yankee Atomic Electric for Sandia National Laboratory. All axial burnup profiles were calculated from 3-D depletion analyses of the core configuration. The organizations and utilities providing axial burnup profiles for the database used different model codes for the 3D-depletion calculations. The model codes used were: SIMULATE-3, NEMO, ANC, and PRESTO-II. Cross-section inputs describing the assemblies are derived from assembly lattice calculations. SIMULATE and NEMO used CASMO-3, ANC and PHOENIX, PRESTO-II used RECORD. The nodal calculations were performed typically in a quarter core symmetric configuration using 12 to 25 nodes to describe the axial direction and one to four nodes to describe the radial direction of each assembly.

5. APPLICATION OF THE DATA

The main objective of the database is to provide a detailed characterization of spent PWR fuel, specifically with respect to the axial burnup distribution.

6. SOURCE AND SCOPE OF DATA

This database contains axial burnup distributions for pressurized water reactors. Data used comprise the name of the utility, the plant name, the vendor, fuel assembly lattice size, fuel vendor, fuel initial enrichment, initial Uranium mass, a serial number used to uniquely identify the profile and assembly attributes. The data cover a range of burnup from slightly over 3 GWd/MTU to 55.3 GWd/MTU and an enrichment range of 1.24 w/o to 4.75 w/o U-235. Fuel designs contain different poison absorbers such as borosilicate glass, B4C, Integral Fuel Burnable Absorber (IFBA), Erbium and Gadolinium. The database consists of 3169 computed axial burnup profiles, covering 106 cycles of operation. 1334 concern profiles of B&W 15x15 fuel design, 544 concern CE 14x14 fuel design, 228 concern CE 16x16 fuel design, 156 concern Westinghouse 15x15 fuel design and 907 concern 17x17 fuel design.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

The data are distributed in an ASCII text file and a CommaSeperatedValues (CSV) file which may be opened with Microsoft Excel-97.

8. DATA FORMAT AND COMPUTER

ASCII/Excel (D00201MNYCP00).

9. TYPICAL RUNNING TIME

Run time varies with the speed of the computer.

10. REFERENCE

R. J. Cacciapouti and S. Van Volkinburg, "Axial Burnup Profile Database for Pressurized Water Reactors," YAEC-1937 (May 1997).

11. CONTENTS OF LIBRARY

Included are the referenced document and one CD rom which includes the database and report written in a self-extracting compressed DOS file.

12. DATE OF ABSTRACT

September 2000.

KEYWORDS: BURNUP; DATABASE