NUCENG 156
Introduction to MCNP and Nuclear Criticality Safety
This course provides an introduction to MCNP and the field of nuclear criticality safety. Topics include: a review of basic concepts related to criticality (fission, cross sections, multiplication factor, etc.); criticality safety accidents; standards applicable to criticality safety; hand calculations and Monte Carlo methods used in criticality safety analysis; criticality safety evaluation documents.
Topics
- The objective of this course is to acquaint Nuclear Engineering students with the concepts and practice of nuclear criticality safety, and to help prepare them for a future career in this field.
- At the end of this course, students should be able to: Explain and define criticality safety factors for operations. Discuss previous criticality accidents and their causal factors, including parameters involved in solution and metal critical accidents. Identify and discuss the application of several common hand calculation methods. Describe the importance of validation of computer codes and how it is accomplished. Discuss ANSI/ANS criticality safety regulations. Describe DOE regulations and practices in the nuclear criticality safety field. Complete a Criticality Safety Evaluation.
Official catalogue course objectives and student learning outcomes
Sources
- Course catalogue ↗2026-2027