Neutron detection by measuring capture gammas in a calorimetric approach

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.

[1]  P. Reeder Neutron detection using GSO scintillator , 1994 .

[2]  M. Divadeenam,et al.  Neutron cross sections , 1981 .

[3]  A. Ferrari,et al.  The n_TOF Total Absorption Calorimeter for neutron capture measurements at CERN , 2009 .

[4]  F. Bečvář,et al.  Simulation of γ cascades in complex nuclei with emphasis on assessment of uncertainties of cascade-related quantities , 1998 .

[5]  R. E. Bolz,et al.  CRC Handbook of tables for Applied Engineering Science , 1970 .

[6]  G. Pausch,et al.  Multifunctional application of pulse width analysis in a LED-stabilized digital NaI(Tl) gamma spectrometer , 2005, IEEE Nuclear Science Symposium Conference Record, 2005.

[7]  Luke E. Erikson,et al.  Lithium Loaded Glass Fiber Neutron Detector Tests , 2009 .

[8]  Lee T. Harding,et al.  Neutron Detection With Gamma-Ray Spectrometers for Border Security Applications , 2010, IEEE Transactions on Nuclear Science.

[9]  B. Lott,et al.  A combination of two 4π detectors for neutrons and charged particles.: Part I. The Berlin neutron ball—a neutron multiplicity meter and a reaction detector , 2003 .

[10]  M. Moszynski,et al.  /sup 6/LiI(Eu) in neutron and /spl gamma/-ray spectrometry-a highly sensitive thermal neutron detector , 2005, IEEE Transactions on Nuclear Science.

[11]  B. Baramsai Neutron Capture Reactions on Gadolinium Isotopes , 2010 .

[12]  M. Moszynski,et al.  Further Study of Boron-10 Loaded Liquid Scintillators for Detection of Fast and Thermal Neutrons , 2010, IEEE Transactions on Nuclear Science.

[13]  Anthony J. Peurrung,et al.  Radiation detector materials: An overview , 2008 .