Neutron reflector analysis for the beam-port of the Missouri S&T Reactor

• Published in: Journal of radioanalytical and nuclear chemistry 2019-11, Vol.322 (2), p.975-981
• Main Authors: Akyurek, Tayfun, Vaz, Warren S., Alajo, Ayodeji B., King, Jeffrey C., Usman, Shoaib, Giraldo, Carlos H. C.
• Format: Article
• Language: English
• Subjects: Aluminum; Analysis; Bismuth; Chemistry; Chemistry and Materials Science; Computer simulation; Diagnostic Radiology; Feasibility studies; Hadrons; Heat transmission; Heavy Ions; Inorganic Chemistry; Materials selection; Monte Carlo simulation; Neutron beams; Neutron flux; Neutrons; Nickel; Nuclear Chemistry; Nuclear Physics; Physical Chemistry; Ports; Radiography; Reflectors; Stainless steels
• ISSN: 0236-5731; 1588-2780
• DOI: 10.1007/s10967-019-06752-x

A preliminary neutron reflector material selection and feasibility study of an inexpensive reflector replacement for the neutron beam-port at the 200 kW Missouri University of Science and Technology Research Reactor (MSTR) was conducted using Monte-Carlo techniques. The Monte-Carlo N-Particle transport code (MCNP6.1) was used to model the neutron beam-port of the Missouri S&T Reactor in order to study the effects of adding different reflector materials, in terms of the neutron flux reaching the radiography/tomography facility in front of MSTR’s neutron beam-port. Aluminum, beryllium, titanium, nickel, nickel-58, lead, bismuth, tungsten and stainless steel reflectors were modeled to find the best neutron reflector for the beam-port. After examining reflector materials, it was concluded that none of them were an improvement over the current design. Experimental thermal flux was measured to be 1.0 × 10 7  ± 3.16 × 10 3  cm −2  s −1 at the exit of beam port for current version of beam-port. The current ratio of beam port inlet and outlet obtained from simulations was found to be 3.37 × 10 4 . The flux of beam port inlet was determined on the order of 1.0 × 10 11  cm −2  s −1 which is consistent with previous findings.