last modified: 06-MAY-2002 | catalog | categories | new | search |

USCD1219 ZZ-PWR-AXBUPRO-SNL.

ZZ PWR-AXBUPRO-SNL, Computed Axial Burnup Profile Database for PWR

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1. NAME OR DESIGNATION:  ZZ-PWR-AXBUPRO-SNL.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
ZZ-PWR-AXBUPRO-SNL USCD1219/01 Arrived 06-MAY-2002

Machines used:

No specified machine
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3. DESCRIPTION OF PROGRAM OR FUNCTION

This database contains axial burnup distributions for pressurised water reactors. The data were obtained directly from utilities whose reactors represent the range of commercial PWR fuel lattices. 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.
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4. METHODS

All axial burnup profiles were calculated from 3-D depletion analyses of the core configuration. The organisation 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.
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9. STATUS
Package ID Status date Status
USCD1219/01 06-MAY-2002 Masterfiled Arrived
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10. REFERENCES
USCD1219/01, included references:
- R.J. Cacciapouti and S.Van Volkinburg:
Axial Burnup Profile Database for Pressurized Water Reactors
YAEC-1937 (May 1997)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

         Yankee Atomic Electric Company
         Nuclear Services Division
         580 Main Street
         Bolton, Massachussetts 01740
         U.S.A.
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16. MATERIAL AVAILABLE
USCD1219/01
DATABASE.TXT Database
PWR_DATA.CSV
ZZ-PWR-AXBUPRO-SNL.PDF Report in PDF Acrobat format
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: axial, burnup, data, pressurized water reactor.