Finding Neutron Detector Efficiency Using Monte Carlo Neutron Particle (MCNP) Calculations

Authors

Eva Wilcox, Brigham Young University
Dr. Lawrence Rees, Brigham Young University

Keywords

neutron detector efficiency, Monte Carlo Neutron Particle, MCNP

College

Physical and Mathematical Sciences

Department

Physics and Astronomy

Abstract

A neutron detector, made by Bart Czirr, has components of plastic and a new compound called lithium gadolinium borate, with a chemical formula of LiGd(BO3)3:Ce3+.

Recommended Citation

Wilcox, Eva and Rees, Dr. Lawrence (2014) "Finding Neutron Detector Efficiency Using Monte Carlo Neutron Particle (MCNP) Calculations," Journal of Undergraduate Research: Vol. 2014: Iss. 1, Article 1253.
Available at: https://scholarsarchive.byu.edu/jur/vol2014/iss1/1253