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NEA-1663 PLUTON.

PLUTON, Isotope Generation and Depletion in Highly Irradiated LWR Fuel Rods

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1. NAME OR DESIGNATION OF PROGRAM:  PLUTON.
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2. COMPUTERS
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Program name Package id Status Status date
PLUTON NEA-1663/01 Tested 01-JUL-2003

Machines used:

Package ID Orig. computer Test computer
NEA-1663/01 PC Windows PC Pentium III,PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The PLUTON-PC is a three-group neutronic code analyzing, as functions of time and burnup, the change of radial profiles, together with average values, of power density, burnup, concentration of trans-uranium elements, plutonium buildup, depletion of fissile elements, and fission product generation in water reactor fuel rod with standard UO2 , UO2-Gd2O3 , inhomogeneous MOX, and UO2-ThO2 . The PLUTON-PC code, which has been designed to be run on Windows PC, has adopted a theoretical shape function of neutron attenuation in pellet, which enables users to perform a very fast and accurate calculation easily. The code includes the irradiation conditions of the Halden Reactor which gives verification data for the code. Verification has been performed up to 83 GWd/tU, and a satisfactory agreement has been obtained.
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4. METHODS

Based upon cumulative yields, the PLUTON-PC code calculates as a function of radial position and local burnup concentrations of fission products, macroscopic scattering cross-sections and self-shielding effect which is important for standard fuel (for Pu242 mainly) and more importantly for homogeneous and inhomogeneous MOX fuel because of higher concentrations of fissile and fertile isotopes of plutonium. The code results in burnup dependent fission rate density profiles throughout the in-reactor irradiation of LWR fuel rods. The isotopes included in calculations have been extended to cover all trans-uranium groups (plutonium plus higher actinides) of fissile and fertile isotopes. Self-shielding problem and scattering effects have been revised and solved for all isotopes in the calculations for adequacy at high burnup, different irradiation conditions and cladding materials.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME:  Less than 1 minute in the sample test case.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-1663/01 01-JUL-2003 Tested at NEADB
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10. REFERENCES

- Sergei E. Lemehov, Jinichi Nakamura, and Suzuki Motoe:
"PLUTON: A Three-Group Model for the Radial Distribution of Plutonium, Burnup, and Power Profiles in Highly Irradiated LWR Fuel Rods,"
Nuclear Technology, Vol. 3, No. 2, (2001) pp.153-168.
NEA-1663/01, included references:
- Sergei E. Lemehov and Motoe Suzuki:
PLUTON - Three-Group Neutronic code for Burnup Analysis of Isotope Generation
and Depletion in Highly Irradiated LWR Fuel Rods
JAERI-Data/Code 2001-025 (August 2001)
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11. HARDWARE REQUIREMENTS:  Windows PC (IBM/PC AT).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1663/01 FORTRAN-90
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13. SOFTWARE REQUIREMENTS

Windows98, Windows-Me, Windows-NT4.0, Windows 2000 professional. FORTRAN-90  (Compiler=Compaq Digital Visual Fortran).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

   Sergei Lemehov
   Russian Research Center "Kurchatov Institute",
   Kurchatov Square 1,  123182, Moscow, Russian Federation
   Tel: 7-095-943-0492,  Fax: 7-095-943-0074

   Suzuki Motoe
   Department of Reactor Safety Research,  
   Tokai Establishment
   Japan Atomic Energy Research Institute
   Tokai-mura, Ibaraki-ken, 319-1195 Japan
   motoe@popsvr.tokai.jaeri.go.jp
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16. MATERIAL AVAILABLE
NEA-1663/01
PLUTON Installing Guide-E.doc Installation note in English
PLUTON Installing Guide-E.doc Installation note in Japanese
PLUTON2 Release note.doc Note on PLUTON2 code
PlutonWin.exe Executable file
Program Abstract.doc Abstract of PLUTON
\INP\ Sample input files directory
\JAERI Report(Data-Code 2001-025)\ Report in Word format
\SRC\ Source files
\PlutonWin\Release\ Object files and executable program compiled with DVF
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, depletion, fission, inventories, isotopes, light-water reactors, neutronics.