Changho Lee
Nuclear Engineering Division
Argonne National Laboratory

Title
Development Activities of Advanced Neutronics Simulation Tools at Argonne National Laboratory

Abstract
Neutronics design and analysis work is the most important step to ensure that a nuclear reactor is operated as designed in terms of power demand, economy, and safety. Neutronics codes developed by Argonne National Laboratory have played a leading role in neutronics design and analysis of fast reactors for many decades. For recent years, significant efforts have been made on developing a high-fidelity deterministic neutronics code named PROTEUS under the DOE NEAMS program. Based on unstructured mesh geometry representations, PROTEUS allows simulation of complex geometry reactors and provides fine resolution, robust and accurate solutions. The presentation will introduce Argonne neutronics tools, focusing on the development activities of high-fidelity neutronics simulation codes at Argonne.

Bio 
Dr. Changho Lee (pictured right) received his BS and MS degrees in Nuclear Engineering from Seoul National University in Korea and his PhD in Nuclear Engineering from Purdue University in 2001. He has over 20 years of experiences in developing neutronics analysis codes at Korea Atomic Energy Research Institute, Purdue University, Westinghouse Electric Co., and Argonne National laboratory. Recently, at Argonne National Laboratory Recently, he developed the multigroup cross section generation code MC²-3 and made a significant contribution to the development of the high-fidelity neutron transport code PROTEUS. He is currently the manager of the Neutronics and Codes Section of the Nuclear Engineering Division at Argonne and the SHARP neutronics lead of the DOE NEAMS program.