# Analysis and characterization of perforated neutron detectors

method linking the MCNP transport code and a specialized ion-transport code to

calculate the probability that a neutron is detected. Channel, chevron, and sinusoidal perforations

are modeled using other customized transport codes. Detector efficiency calculations

are performed for neutrons incident at various polar and azimuthal angles. It is discovered

that the efficiency losses of the detectors result from the decreasing solid angle subtended

by the detector from the source and streaming through the detector at specific azimuthal

angles. Detectors achieving an efficiency in excess of 10% and having a relatively flat ± 1%

angular dependence in all azimuthal angles and polar angles between 0 and 60 degrees are predicted. Efficiencies up to 25% are achievable at the loss of directional independence.

In addition to minimizing the directional dependence of the perforated detectors, the

feasibility of developing a neutron detector for deployment in cargo containers to locate

nuclear weapon pits is investigated using the MCNP transport code. The detector considered

is a 7-mm diameter, 6LiF, rod-perforated detector surrounded in a cylinder of polyethylene.

The optimum thicknesses of surrounding polyethylene, to maximize the response of the

detector, is determined to be 10 cm of radial, 5 cm of front, and 5 cm of back polyethylene

for end-on neutron incidence. Such a detector is predicted to produce a count rate between 12

and 15 cpm from a nuclear-weapon pit composed of 90% 239Pu and 10% 240Pu at a distance

of 3 m. Side incidence is also considered, and the optimum moderator dimensions are 8 cm

of radial, 10 cm of front, and 10 cm of back polyethylene that produce approximately the

same count rate.

Advisor:

School:Kansas State University

School Location:USA - Kansas

Source Type:Master's Thesis

Keywords:monte carlo semiconductor detector neutron perforated radiation engineering nuclear 0552

ISBN:

Date of Publication:01/01/2007