Computer Programs
NEA-1867 RAPID.
last modified: 24-AUG-2011 | catalog | categories | new | search |

NEA-1867 RAPID.

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

top ]
1. NAME OR DESIGNATION OF PROGRAM:  RAPID.
top ]
2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

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
top ]
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.
top ]
4. METHODS

RAPID solves numerically the time and space-dependent differential equations.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None.
top ]
6. TYPICAL RUNNING TIME:  Less than 10 seconds.
top ]
7. UNUSUAL FEATURES:  None.
top ]
9. STATUS
Package ID Status date Status
NEA-1867/01 24-AUG-2011 Tested at NEADB
top ]
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
top ]
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
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1867/01 FORTRAN-IV
top ]
13. SOFTWARE REQUIREMENTS:  This program is executed on MS-Windows.
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
top ]
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
top ]
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
top ]
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.