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PSR-0523 DEPLETOR V.2.

DEPLETOR Version 2, provides depletion capability to the Purdue Advanced Reactor Core Simulator (PARCS) code

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1. NAME OR DESIGNATION OF PROGRAM

DEPLETOR V.2

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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
DEPLETOR V.2 PSR-0523/01 Arrived 04-DEC-2007

Machines used:

Package ID Orig. computer Test computer
PSR-0523/01 PC Windows,SUN W.S.
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3. DESCRIPTION OF PROGRAM OR FUNCTION

DEPLETOR provides depletion capability for the Purdue Advanced Reactor Core Simulator (PARCS), a computer code for predicting the transient behavior of light water reactor cores. PARCS solves the steady-state and time-dependent neutron diffusion equation in three-dimensional geometry to obtain the neutron flux distribution. Because PARCS solves the eigenvalue problem and is capable of performing criticality searches, it can provide the neutron flux distribution required to perform core depletion analysis. PARCS is not included in this code package.

 

DEPLETOR provides the following five functions:

 

  • read in the macroscopic cross sections from PMAXS, the XS file prepared by the interface code GENPXS,

  • calculate region wise macroscopic cross sections as a function of the history state, such as burnup, moderate density history, control rod history,

  • transfer the region wise macroscopic cross sections to PARCS,

  • obtain the region wise fluxes from PARCS,

  • calculate region wise history increment at each step based on fluxes.

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4. METHODS

DEPLETOR generates the cross-sections at each burnup state and transfers them to PARCS, which then solves the diffusion equations with the given macroscopic cross sections and transfers the resulting flux distribution to DEPLETOR. In order to minimize the changes to the PARCS code, DEPLETOR was developed and will be maintained as a separate code. All information transfer between PARCS and DEPLETOR is performed using the standard message passing interface software PVM.

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6. TYPICAL RUNNING TIME

Run times vary depending on the problem and the speed of the computer.

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8. RELATED OR AUXILIARY PROGRAMS

PVM and PARCS are not included in this distribution. PARCS is available through the U. S. Nuclear Regulatory Commission. Information on PVM can be found at: http://www.csm.ornl.gov/pvm/pvm_home.html

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9. STATUS
Package ID Status date Status
PSR-0523/01 04-DEC-2007 Masterfiled Arrived
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10. REFERENCES
  • H. Joo, D. Barber, G. Jiang, and T. Downar:
    PARCS: A Multi-Dimensional Two-Group Reactor Kinetics Code Based on the Nonlinear Analytic Nodal Method (PU/NE-98-26, Purdue University - 1998)

PSR-0523/01, included references:
- Y. Xu and T. J. Downar:
DEPLETOR: A Depletion Code for PARCS, Version 2, Informal Report Purdue
University (May 2003)
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11. HARDWARE REQUIREMENTS

DEPLETOR runs on personal computers running Windows and on Sun workstations.

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0523/01 FORTRAN-90
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13. SOFTWARE REQUIREMENTS

The code is written in Fortran 90 and has been used on Sun workstations and on Pentium computers running Windows. PVM is required for information transfer between PARCS and DEPLETOR. Executables provided by the developers using compilers listed below are included in the distribution. The PC executable was created with Compaq Visual Fortran 6.1A under Windows 2000. The Sun compiler 6.0 was used to create the Sun executable.

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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, USA

 

Developed by:   Purdue University, West Lafayette, Indiana, USA

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16. MATERIAL AVAILABLE
PSR-0523/01
DEPLETOR source code
DEPLETOR executables for PC and Sun
Makefiles and sample problem input and output
Electronic documentation
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, cross sections, depletion, light-water reactors, transients.