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Mitja Majerle, Gael de Cargouet Nuclear Physics Institute Řež, Czech Republic

9 th session of the AER Working Group “f “ - Spent Fuel Transmutations Simulations of experimental “AD S ”. Mitja Majerle, Gael de Cargouet Nuclear Physics Institute Řež, Czech Republic. Supercomputer Cray I. Introduction. Experimental ADS at JINR Dubna High energy protons/deuterons

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Mitja Majerle, Gael de Cargouet Nuclear Physics Institute Řež, Czech Republic

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  1. 9th session of the AER Working Group “f “ - Spent Fuel TransmutationsSimulations of experimental “ADS” Mitja Majerle, Gael de Cargouet Nuclear Physics Institute Řež, Czech Republic Supercomputer Cray I

  2. Introduction • Experimental ADS at JINR Dubna • High energy protons/deuterons • Spallation source (lead) • Optionally moderator • Measurement of neutron fluxes • MCNPX simulations: • Beside standard MCNP : • spallation • high energy neutron transport • Differences experiment-simulation AER Working Group “f “ - Spent Fuel Transmutations

  3. MCNP vs. MCNPX AER Working Group “f “ - Spent Fuel Transmutations

  4. Experimental setups • Accelerator (Nuclotron, Phasotron) + • Target with polyethylene – GAMMA-2 (low energy neutrons< 0.1 MeV) • Bare target – PHASOTRON (high energy neutrons >10 MeV) • Target with uranium blanket - EPT • Target in graphite block – GAMMA-MD AER Working Group “f “ - Spent Fuel Transmutations

  5. What we measure… • Radiochemical detectors • Monoisotopic foils activated by neutrons • Gamma spectrometry • n,xn (10-100 MeV) • n,g (<0.1 MeV) • Solid state nuclear track detectors • Fissile material (Pb, U) + mica foil • Chemical etching • Optical microscopy • n,fission (>100 MeV in Pb) • Radioactive samples • U, Pu, Np, I, … packed in Al • Gamma spectrometry • Mostly n,xn reactions AER Working Group “f “ - Spent Fuel Transmutations

  6. PHASOTRON EXPERIMENT AER Working Group “f “ - Spent Fuel Transmutations

  7. .. and how do we simulate ? • Neutron spectrum is calculated with MCNPX Neutron spectrum from PHASOTRON experiment • Cross-sections calculated with MCNPX/TALYS • (n,xn), (n,g), (n,fission) • Convolution: REACTION RATE=NS*XS AER Working Group “f “ - Spent Fuel Transmutations

  8. PHASOTRON • Simple, clean setup • 660 MeV protons • Radiochemical detectors, samples • Calculations : • HE - good agreement • LE - many influences AER Working Group “f “ - Spent Fuel Transmutations

  9. ENERGY PLUS TRANSMUTATION • Pb target + U blanket • 4 proton beams : • 0.7, 1, 1.5, 2 GeV • 2 deuteron beams: • 2.52, 1.26 GeV • Detectors : • Radiochemical • SSNTD • Samples AER Working Group “f “ - Spent Fuel Transmutations

  10. Calculations (EPT) • Radiochemical: • beam < 1.5 GeV • good agreement HE • beam >= 1.5 GeV • SSNTD: • 1.5 GeV • good agreement Neutrons - 10-100 MeV bad - >100 MeV good AER Working Group “f “ - Spent Fuel Transmutations

  11. GAMMA-MD • Pb target • Graphite block • 2.33 GeV deuterons experiment AER Working Group “f “ - Spent Fuel Transmutations

  12. Low energy neutron spectrum • Experiments aimed towards HE neutrons • Parameters of shileding, concrete walls… are not precisely known • LE results can be used for eg. relative comparison between experiments AER Working Group “f “ - Spent Fuel Transmutations

  13. Summary • Below 1 GeV, calculations are reliable within 30% • Above 1.5 GeV, wrong results for neutrons 10-100 MeV, energies >100 MeV are probably OK (SSNTD) • Possible reasons under investigation (spallation model or XS libraries) ? AER Working Group “f “ - Spent Fuel Transmutations

  14. Parallel computing • Monte-Carlo method can be very well parallelized • MCNPX supports MPI and PVM • Tested on 32bit Xeons (4x) and 64bit Opterons(8x)-speed ca. linearly rises with the number of processors • Plan to try computer farms (grid system) AER Working Group “f “ - Spent Fuel Transmutations

  15. TALYS • TALYS: nuclear reaction software by NRG Petten and CEA Bruyères-le-Châtel. • Energy range 1 keV - 200 MeV. • Neutrons, protons, deuterons, tritons, helions, alphas and photons. • Many nuclear reaction models implemented. • All open nuclear reaction channels covered. • Appropriate for basic physics and applications. AER Working Group “f “ - Spent Fuel Transmutations

  16. TALYS • A friendly program AER Working Group “f “ - Spent Fuel Transmutations

  17. Data produced by TALYS • Total, elastic, Inelastic and reaction cross sections. • Exclusive reaction channels, e.g. (n,p), (n,np). • Exclusive isomeric production cross sections. • Fission cross sections. • Fission yields. • Total particle production cross sections, e.g. (n,xn). AER Working Group “f “ - Spent Fuel Transmutations

  18. Data produced by TALYS • Comparison with experimental data AER Working Group “f “ - Spent Fuel Transmutations

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