Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1505 ZZ-WPPR-1-A/B.
last modified: 12-FEB-2002 | catalog | new | search |

NEA-1505 ZZ-WPPR-1-A/B.

ZZ WPPR, Pu Recycling Benchmark Results

top ]
1. NAME OR DESIGNATION OF PROGRAM:  ZZ-WPPR-1-A/B.
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
ZZ-WPPR-1-A/B NEA-1505/01 Tested 18-MAR-1996
ZZ-WPPR-2-CYC1 NEA-1505/02 Arrived 12-FEB-2002

Machines used:

Package ID Orig. computer Test computer
NEA-1505/01 Many Computers Many Computers
NEA-1505/02 Many Computers
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

The NEA NSC Working Party on Physics of Plutonium Recycling has commissioned a series of benchmarks covering:
- Plutonium recycling in pressurized-water reactors
- Void reactivity effect in pressurized-water reactors
- Fast Plutonium-burner reactors: beginning of life
- Plutonium recycling in fast reactors
- Multiple recycling in advanced pressurized-water reactors.
The results have been published (see references).
ZZ-WPPR-1-A/B contains graphs and tables relative to the PWR Mox pin cell benchmark, representing typical fuel for plutonium recycling, one corresponding to a first cycle, the second for a fifth cycle. These computer readable files contain the complete set of results, while the printed report contains only a subset.
ZZ-WPPR-2-CYC1 are the results from cycle 1 of the multiple recycling benchmarks.
top ]
4. METHOD OF SOLUTION:
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
top ]
6. TYPICAL RUNNING TIME:
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS:
top ]
9. STATUS
Package ID Status date Status
NEA-1505/01 18-MAR-1996 Screened
NEA-1505/02 12-FEB-2002 Masterfiled restricted
top ]
10. REFERENCES

Physics of Plutonium Recycling:
- Issues and Perspectives, Vol. 1 , OECD 1995, ISBN 92-64-14538-9
- Plutonium Recycling in PWRs, Vol. 2 , OECD 1995,
  ISBN 92-64-14590-7
- Void Reactivity Effect in PWRs, Vol. 3 , OECD 1995,
  ISBN 92-64-14591-5
- Fast Plutonium-burner Reactors: Beginning of Life, Vol. 4 ,
  OECD 1995, ISBN 92-64-14703-9
- Plutonium Recycling in Fast Reactors, Vol. 5 ,
  OECD 1995, ISBN 92-64-14704-7
- Multiple Recycling in Advanced PWRs, Vol. 6 , in preparation
top ]
11. MACHINE REQUIREMENTS:
top ]
12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

Phase 1:    D. Lutz, M. Mattes
            Universitaet Stuttgart
            Institut fuer Kernenergetik
            und Energiesysteme
            Postfach 801140
            D-70550 STUTTGART 80
            Germany
Phase 2:    Marc Delpech and Marc Juanola
            CE Cadarache
            DER/SPRC, Bat. 230
            F-13108 ST PAUL LEZ DURANCE
            France
top ]
16. MATERIAL AVAILABLE
NEA-1505/02
test-case data   mag tapeWPPR2-CYC1 Standard PWR EXCEL results 1/2  DATTP
test-case data   mag tapeWPPR2-CYC1 Standard PWR EXCEL results 2/2  DATTP
test-case data   mag tapeWPPR2-CYC1 HM PWR EXCEL results            DATTP
NEA-1505/01
File name File description Records
NEA1505_01.001 Information file 105
NEA1505_01.002 PL_AR_A.PS absorption rate fuel A plot 0
NEA1505_01.003 PL_AR_B.PS absorption rate fuel B plot 0
NEA1505_01.004 PL_FR_A.PS fission rate fuel A plot 0
NEA1505_01.005 PL_FR_B.PS fission rate fuel B plot 0
NEA1505_01.006 PL_SA_A.PS absorption xsec fuel A plot 0
NEA1505_01.007 PL_SA_B.PS absorption xsec fuel B plot 0
NEA1505_01.008 PL_SF_A.PS fission xsec fuel A plot 0
NEA1505_01.009 PL_SF_B.PS fission xsec fuel B plot 0
NEA1505_01.010 PL_TD_A.PS number density fuel A plot 0
NEA1505_01.011 PL_TD_B.PS number density fuel B plot 0
NEA1505_01.012 T_AR_A.PS absorption rate fuel A table 0
NEA1505_01.013 T_AR_B.PS absorption rate fuel B table 0
NEA1505_01.014 T_FR_A.PS fission rate fuel A table 0
NEA1505_01.015 T_FR_B.PS fission rate fuel B table 0
NEA1505_01.016 T_NU_A.PS nu-bar fuel A table 0
NEA1505_01.017 T_NU_B.PS nu-bar fuel B table 0
NEA1505_01.018 T_SA_A.PS absorption xsec fuel A table 0
NEA1505_01.019 T_SA_B.PS absorption xsec fuel B table 0
NEA1505_01.020 T_SF_A.PS fission xsec fuel A table 0
NEA1505_01.021 T_SF_B.PS fission xsec fuel B table 0
NEA1505_01.022 T_TD_A.PS number density fuel A table 0
NEA1505_01.023 T_TD_B.PS number density fuel B table 0
NEA1505_01.024 AR_A.ASC absorption rate fuel A ASCII file 567
NEA1505_01.025 AR_B.ASC absorption rate fuel B ASCII file 527
NEA1505_01.026 FR_A.ASC fission rate fuel A ASCII file 245
NEA1505_01.027 FR_B.ASC fission rate fuel B ASCII file 228
NEA1505_01.028 NU_A.ASC nu-bar fuel A table ASCII file 245
NEA1505_01.029 NU_B.ASC nu-bar fuel B table ASCII file 228
NEA1505_01.030 SA_A.ASC absorption xsec fuel A ASCII file 527
NEA1505_01.031 SA_B.ASC absorption xsec fuel B ASCII file 487
NEA1505_01.032 SF_A.ASC fission xsec fuel A ASCII file 228
NEA1505_01.033 SF_B.ASC fission xsec fuel B ASCII file 211
NEA1505_01.034 TD_A.ASC number density fuel A ASCII file 527
NEA1505_01.035 TD_B.ASC number density fuel B ASCII file 487
top ]
17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: fuel cycle, fuel management, life-cycle cost, nuclear materials management, plutonium, reprocessing.