Title :
Calculation of the performance of 3He alternative detectors with MCNPX
Author :
Swinhoe, M.T. ; Hendricks, J.S.
Author_Institution :
Safeguards Sci. & Technol. Group, Los Alamos Nat. Lab., Los Alamos, NM, USA
Abstract :
This paper describes the techniques that are available to calculate the performance of 3He alternative detectors using MCNPX. Calculations of the performance of safeguards detectors that use 3He have been successfully carried out for many years. In the case of coincidence or multiplicity counting, specific tallies have been implemented to calculate the Singles, Doubles and Triples counting rates. The implementation of the method was done in such a way that it equates every capture in some nuclide in the detection zone with the production of an electronic pulse from the detector. This is a very good approximation for 3He detectors and BF3 detectors. However it is not appropriate for detectors such as boron-lined proportional counters, in which the fraction of capture events leading to an electronic pulse above threshold is very dependent on the geometric arrangement, in particular the thickness and composition of the boron-containing layer. This paper gives calculations of the ideal pulse height distributions to be expected from different detector types and gives values for the probability, as a function of detector energy threshold, that a neutron capture reaction will cause an electronic pulse from the detector. This is termed the electronic efficiency. This electronic detection efficiency depends very little on the energy of the captured neutron, which in most practical cases are heavily weighted towards thermal energies. It does not depend on the position of the source neutron or moderation in the sample. For cases of interest to nuclear safeguards, measurement of uranium and plutonium in specially designed detectors, the spectrum of detected neutrons is fairly constant and thus the electronic detection efficiency becomes a detector constant. The paper discusses how the electronic detection efficiency needs to be included in the calculation of Singles, Doubles and Triples, and describes proposals to improve the tallying capability of MCNPX for such cases.
Keywords :
Monte Carlo methods; coincidence techniques; helium-3 counters; neutron detection; nuclear electronics; pulse height analysers; 3He alternative detector; BF3 detectors; MCNPX; captured neutron; detection zone; detector coincidence; detector constant; detector energy threshold; double counting rate; electronic detection efficiency; electronic pulse production; geometric arrangement; multiplicity counting; neutron capture reaction; neutron detection; nuclear safeguards; plutonium measurement; pulse height distributions; safeguards detectors; single counting rate; thermal energies; triple counting rate; uranium measurement; Boron; Detectors; Electron tubes; Logic gates; Materials; Mathematical model; Neutrons;
Conference_Titel :
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2011 2nd International Conference on
Conference_Location :
Ghent
Print_ISBN :
978-1-4577-0925-8
DOI :
10.1109/ANIMMA.2011.6172919