NEA-1867 RAPID.

RAPID, RAdial power and burnup Prediction by following fissile Isotope Distribution in the pellet

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHODS, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES, STATUS, REFERENCES, HARDWARE REQUIREMENTS, LANGUAGE, SOFTWARE REQUIREMENTS, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: RAPID.

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2. COMPUTERS

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Program name	Package id	Status	Status date
RAPID	NEA-1867/01	Tested	24-AUG-2011

Machines used:

Package ID	Orig. computer	Test computer
NEA-1867/01	IBM PC	IBM PC

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3. DESCRIPTION OF PROGRAM OR FUNCTION

The RAPID (RAdial power and burnup Prediction by following fissile Isotope Distribution in the pellet) model was developed to predict the radial distribution of power, burnup and fissionable nuclide densities in the LWR UO2 fuel pellets to be used in the fuel performance analysis code. It considers the specific radial variations of the neutron reactions of all the fissionable nuclides as a function of burnup and 235U enrichment in the pellet. Comparison of the RAPID prediction with the measured data of the irradiated fuels and the predicted results by other codes showed good agreement, and therefore, the RAPID model can be used for the UO2 fuel of up to 10 w/o 235U enrichment and 150 MWD/kgU pellet average burnup under the LWR environment.

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4. METHODS

RAPID solves numerically the time and space-dependent differential equations.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM: None.

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6. TYPICAL RUNNING TIME: Less than 10 seconds.

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7. UNUSUAL FEATURES: None.

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9. STATUS

Package ID	Status date	Status
NEA-1867/01	24-AUG-2011	Tested at NEADB

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10. REFERENCES

NEA-1867/01, included references:

- Chan Bock Lee, Jae Seung Song, Je Gun Bang, Dae Ho Kim and Youn Ho Jung:
RAPID model to predict radial burnup distribution in LWR UO2 fuel, J. of
nuclear materials, 279, 207-215, 2000

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11. HARDWARE REQUIREMENTS: IBM PC.

NEA-1867/01

Tested at the NEA Databank on:
- COMPUTER : Dell Workstation PWS670, XEON, 2.66 GHz
- OPERATING SYSTEM : DOS, under Windows XP Pro
- COMPILER: Compaq Visual Fortran Professional Edition 6.6a

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-1867/01	FORTRAN-IV

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13. SOFTWARE REQUIREMENTS: This program is executed on MS-Windows.

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

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15. NAME AND ESTABLISHMENT OF AUTHORS

Chan Bock LEE
Korea Atomic Energy Research Institute (KAERI)
Yusung P.O. Box 105
Daejeon 305-600
REPUBLIC OF KOREA

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16. MATERIAL AVAILABLE

NEA-1867/01

RAPID fortran source program with instruction description to use program
RAPID execution file
Sample input
Sample output
Reference journal paper

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17. CATEGORIES

F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
W. Physics

Keywords: LWR reactors, fuel behaviour, fuel pellets, high burnup structure, uranium 235, uranium dioxide, uranium fuels.