Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects

NEA-1505 ZZ-WPPR-1-A/B&2-CYC1

last modified: 12-FEB-2002 | catalog | new | search |

NEA-1505 ZZ-WPPR-1-A/B&2-CYC1

ZZ WPPR-1-A/B and ZZ WPPR-2-CYC1, Pu Recycling Benchmark Results

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: ZZ-WPPR-1-A/B and ZZ-WPPR-2-CYC1

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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

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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.

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4. METHOD OF SOLUTION:

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

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6. TYPICAL RUNNING TIME:

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7. UNUSUAL FEATURES OF THE PROGRAM:

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8. RELATED AND AUXILIARY PROGRAMS:

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9. STATUS

Package ID	Status date	Status
NEA-1505/01	18-MAR-1996	Tested restricted
NEA-1505/02	12-FEB-2002	Masterfiled restricted

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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

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11. MACHINE REQUIREMENTS:

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12. PROGRAMMING LANGUAGE(S) USED

No specified programming language

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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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

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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

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17. CATEGORIES

Y. Integral Experiments Data, Databases, Benchmarks

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