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This course provides a detailed discussion over the fundamental concepts associated with the Monte Carlo (MC) method for particle/radiation transport. Students will be able to learn the fundamental and advanced topics on the application of MC to solve radiation transport problems in nuclear engineering. Applications of generalized MC techniques using the MCNP code to solve neutron, photon, and electron radiation transport problems typically encountered in reactor physics, shielding, criticality safety, and radiation dosimetry will be addressed. The students will also learn how to use the MCNP code to solve these problems. Students will improve their programming skills for Monte Carlo particle transport and statistical analysis. Therefore, a basic understanding of nuclear reactor physics is highly recommended. Also, students in this class are expected to have some undergraduate-level background in Probability and Statistics. Also, programming experience (e.g., Python, MATLAB) is highly recommended.

Typically offered in Fall only