Title :
Portable neutron energy spectrometer utilizing microstructured semiconductor neutron detectors (MSND)
Author :
Cooper, B.W. ; Bellinger, S.L. ; Bolding, Simon R. ; Caruso, A. ; Fronk, R.G. ; Miller, W.H. ; Oakes, Thomas M. ; Shultis, S. Kenneth ; Sobering, Timothy S. ; Taylor, Russell ; Huddleston, David ; McGregor, D.S.
Author_Institution :
SMART Lab., Kansas State Univ., Manhattan, KS, USA
fDate :
Oct. 27 2012-Nov. 3 2012
Abstract :
The portable neutron energy spectrometer is designed to identify an unknown neutron source. The spectrometer is cylindrical in shape with a diameter of 12 cm and a length of 33 cm. This allows for a large surface area for incident neutrons to interact with and sufficient moderating material to thermalize neutrons up to 14.1 MeV in energy. The spectrometer utilizes eleven 2 cm × 2 cm high-efficiency microstructured semiconductor neutron detector (MSND) devices. The detectors are arranged linearly along the central axis of the spectrometer. The spectrometer´s volume consists of alternating layers of MSNDs, high-density polyethylene (HDPE), and cadmium. The HDPE acts as a moderator for the epithermal and fast neutrons, allowing them to disperse energy linearly within the spectrometer´s volume thereby, becoming thermalized and counted by the detectors. The 2 mm thick cadmium layer after each detector prevents thermal neutrons from backscattering to a previous detector. Extensive modeling of the portable spectrometer was conducted using MCNPS. The modeling was used to optimize the number of MSNDs and the thickness of the HDPE layers. Also, reference library templates for a variety neutron sources were simulated, including; 252Cf, 252Cf + D2O, PuBe, AmBe, and a 14.1 MeV fusion neutron source. A Figure-of-Merit calculation was used to identify the experimental neutron source. The spectrometer is a light-weight, portable, self-contained unit, weighing less than 20 lbs. It is powered by a rechargeable 6V battery contained within the main housing. The measurement data and identified neutron source information is displayed on the built-in LCD screen.
Keywords :
Monte Carlo methods; neutron detection; neutron sources; neutron spectrometers; semiconductor counters; 252Cf-D2O; AmBe; HDPE moderator; MCNPS based portable spectrometer modeling; PuBe; alternating MSND layers; cadmium layer; cylindrical spectrometer; electron volt energy 14.1 MeV; epithermal neutrons; fast neutrons; figure of merit calculation; fusion neutron source; high density polyethylene; high efficiency MSND devices; microstructured semiconductor neutron detectors; moderating material; neutron sources; neutron thermalisation; portable neutron energy spectrometer; size 12 cm; size 2 cm; size 2 mm; size 33 cm; spectrometer volume; unknown neutron source identification;
Conference_Titel :
Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC), 2012 IEEE
Conference_Location :
Anaheim, CA
Print_ISBN :
978-1-4673-2028-3
DOI :
10.1109/NSSMIC.2012.6551972