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Neutron Studies in Edelweiss: Geant3 and MCNPX Simulation Comparisons

This report presents the findings from neutron studies in the Edelweiss experiment, held in Valencia, Spain on April 15, 2005. It details the angular distribution of germanium nuclear recoil as simulated with Geant3 and MCNPX, alongside a comprehensive analysis of rock spectra propagation. The study uses the TALYS code for calculating differential cross-sections and highlights the effective neutron calibration with 232Cf. Results indicate a good agreement between simulation data and theoretical predictions, emphasizing the need for continued comparisons to refine understanding of discrepancies.

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Neutron Studies in Edelweiss: Geant3 and MCNPX Simulation Comparisons

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  1. Ilias/N3/WG5 meeting Maryvonne De Jésus Neutron studies in Edelweiss “Suite” Valencia (Espana) 15/04/2005

  2. Plan • Germanium nuclear recoil angular distribution in Geant 3 • Rock spectra propagation with Geant 3 and MCNPX

  3. Correction : Code THALYS used to calculate differential cross sections in the CM with Koning-Delaroche set of parameters and spherical nuclei (O. Bersillon , private communication : Proper reference to the code TALYS A.J. Koning, S. Hilaire and M. Duijvestijn, TALYS: Comprehensive nuclear reaction modeling Proceedings of the International Conference on Nuclear Data for Science and Technology - ND2004 Sep. 26 - Oct. 1, Santa Fe, USA, to be published Proper reference to the optical model parameters for germanium A.J. Koning and J.P. Delaroche Local and global nucleon optical models from 1 keV to 200 MeV Nuclear Physics A 713 (2003) 231-310) Angular distribution with Geant 321

  4. Modification in the SUBROUTINE COLISN IF (KZI.eq.32) call MYCANG

  5. Edelweiss-I neutron calibration with 232Cf Simulation with modified Geant-321 • Ratio Data/Simulation [15 , 200 ] keV : 1.5 • Data vs. simulation : good agreement in the nuclear recoil spectra

  6. Propagation of neutrons through the LSM rock : Geant3 and MCNPX • Initial rock spetra : • Spectrum calculated by V.Chazal (Astroparticle Phys.9 (1996)163-172 ) • Neutron production in the rock : f=1.143x10e-7 n/s/cm3 • Neutron flux in lab reevaluated • (G.Chardin et al IDM 2002 ) En > 2 MeV : f= 1.6x10-6 n/s/cm2 • Spectrum calculated by R.Lemrani with code SOURCES : • Neutron production in the rock : f=1.133x10e-7 n/s/cm3 Measured rock composition : Density : r=2.65 g/cm3 Rock composition introduced in Geant 3

  7. Rock Lab Air or PE Geometries for simulations with geant3 : Plane geometry

  8. Geant 3 Geant 3 Geant 3 V.Chazal V.Chazal V.Chazal SOURCES SOURCES SOURCES MCNPX MCNPX MCNPX Results : LSM Geometry with scatterring LSM Geometry with scatterring LSM Geometry without scatterring Plane Geometry

  9. Results : Plane + 60 cm polyethylene : reduction factor of ~ 15000 f= ~ 13x10-10

  10. Summary and outlook • Relatively good agreement between the 2 codes G3 and MCNP • Continue code comparisons to understand the remaining • discrepancies • Propagate the lab n spetrum through EDW-1 and EDW-II • geometries to get correct nuclear recoil spectra for Germanium .

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