• Title of article

    Monte Carlo simulation of the n_TOF Total Absorption Calorimeter

  • Author/Authors

    Guerrero، نويسنده , , C. and Cano-Ott، نويسنده , , D. and Mendoza، نويسنده , , E. and Taيn، نويسنده , , J.L. and Algora، نويسنده , , A. and Berthoumieux، نويسنده , , E. and Colonna، نويسنده , , N. and Domingo-Pardo، نويسنده , , C. and Gonzلlez-Romero، نويسنده , , E. and Heil، نويسنده , , Lorena M. and Jordلn، نويسنده , , D. and Kنppeler، نويسنده , , F. and Lampoudis، نويسنده , , C. and Martيnez، نويسنده , , T. and Massimi، نويسنده , , C. ، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2012
  • Pages
    10
  • From page
    108
  • To page
    117
  • Abstract
    The n_TOF Total Absorption Calorimeter (TAC) is a 4 π BaF2 segmented detector used at CERN for measuring neutron capture cross-sections of importance for the design of advanced nuclear reactors. This work presents the simulation code that has been developed in GEANT4 for the accurate determination of the detection efficiency of the TAC for neutron capture events. The code allows to calculate the efficiency of the TAC for every neutron capture state, as a function of energy, crystal multiplicity, and counting rate. The code includes all instrumental effects such as the single crystal detection threshold and energy resolution, finite size of the coincidence time window, and signal pile-up. sults from the simulation have been validated with experimental data for a large set of electromagnetic de-excitation patterns: β - decay of well known calibration sources, neutron capture reactions in light nuclei with well known level schemes like natTi, reference samples used in ( n , γ ) measurements like 197Au and experimental data from an actinide sample like 240Pu. The systematic uncertainty in the determination of the detection efficiency has been estimated for all the cases. As a representative example, the accuracy reached for the case of 197Au( n , γ ) ranges between 0.5% and 2%, depending on the experimental and analysis conditions. Such a value matches the high accuracy required for the nuclear cross-section data needed in advanced reactor design.
  • Keywords
    Monte Carlo simulation , Neutron cross-sections , GEANT4 , Time-of-flight , Neutron capture
  • Journal title
    Nuclear Instruments and Methods in Physics Research Section A
  • Serial Year
    2012
  • Journal title
    Nuclear Instruments and Methods in Physics Research Section A
  • Record number

    2205758