• DocumentCode
    3530811
  • Title

    Neutron detection by measuring capture gammas in a calorimetric approach

  • Author

    Herbach, Claus-Michael ; Pausch, Guntram ; Kreuels, Achim ; Kong, Yong ; Lentering, Ralf ; Plettner, Cristina ; Roemer, Katja ; Scherwinski, Falko ; Schotanus, Paul ; Stein, Juergen ; Teofilov, Nikolai ; Wilpert, Thomas

  • Author_Institution
    ICx Technol. GmbH, Dresden, Germany
  • fYear
    2010
  • fDate
    Oct. 30 2010-Nov. 6 2010
  • Firstpage
    1827
  • Lastpage
    1834
  • Abstract
    Radiation detector systems for homeland security applications have been usually equipped with 3He tubes to detect the distinguished neutron signature of Special Nuclear Materials (SNMs). The serious shortage of 3He gas, however, recently initiated substantial efforts to develop alternative neutron detectors, particularly for large-area Radiation Portal Monitors (RPMs). Most activities are currently directed to detectors comprising 6Li or 10B - beyond doubt with remarkable success. Nevertheless, their broad deployment poses an economic challenge. Our contribution presents a different technique - the detection of neutron capture gammas. In contrast to other attempts we do not focus on characteristic gammas or conversion electrons in the low-energy range, or on the detection of single high-energy capture gammas. Rather we propose to measure the sum energy of multiple gammas released after neutron capture reactions in a semi-calorimetric approach. This method allows simultaneous measurements of neutron and gamma radiation with a single detector (even including spectroscopic information for nuclide identification). A first prototype of such a Neutron Capture Detector (NCD) was developed based on proven standard detector materials and technologies. It consists of thin Cadmium sheets surrounded by four BGO scintillation crystals. The detector response was studied in measurements with cold neutrons extracted at the BER II reactor, and with fission neutrons from 252Cf. The NCD performance is discussed in comparison with those of a 3He tube. Simulation calculations have been performed to estimate the detection efficiency as a function of the detector size. A complete database to model the multiple-gamma emission from excited 114Cd nuclei was composed by a semi-empirical approach which combines the gamma energies and yields of well resolved transitions with information from integral measurements. The - - simulation results are validated experimentally and allow optimizing more complex NCD systems for RPM applications.
  • Keywords
    gamma-ray detection; helium-3 counters; neutron detection; neutron radiative capture; particle calorimetry; solid scintillation detectors; 10B; 252Cf; 3He tubes; 6Li; BGO scintillation crystals; NCD; Neutron Capture Detector; RPM; SNM; Special Nuclear Materials; cadmium sheets; calorimetric approach; capture gamma measurement; cold neutrons; detector size; excited 114Cd nuclei; fission neutrons; gamma radiation; homeland security applications; large-area Radiation Portal Monitors; neutron capture gammas; neutron capture reactions; neutron detection; neutron signature; nuclide identification; radiation detector systems; semi-empirical approach; Crystals; Data models; Detectors; Energy measurement; Neutrons; Tin;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Nuclear Science Symposium Conference Record (NSS/MIC), 2010 IEEE
  • Conference_Location
    Knoxville, TN
  • ISSN
    1095-7863
  • Print_ISBN
    978-1-4244-9106-3
  • Type

    conf

  • DOI
    10.1109/NSSMIC.2010.5874091
  • Filename
    5874091