We are solving various nuclear engineering problems using computational codes such as particle transport analysis, advanced reactor core design and analysis, spent fuel characterization, critical safety, and so on. Also, we are developing computational methods and codes for nuclear engineering problems. The Followings are a summary of the research area:
- Development of advanced computational methods and codes for particle transport and reactor physics analysis
- Parallel computations using LINUX clusters (Monte Carlo particle transport) for radiation and activation analysis for accelerators, reactor systems, and fusion facilities
- Conceptual design of advanced reactor cores (PWRs, SMRs, Gen IV fast reactors)
- Engineering design and analysis for criticality safety, radiation shielding, and activation
- Development of multi-group cross-section generation method and library generation codes
- Development of automatic source term generation code for spent fuel facilities

AMD EPYC 7352 24-core processor 5-node clustering
AMD Opteron(tm) 6284 SE 16-core processor 8-node clustering
Intel Xeon(R) E5-2690 v4 14-core processor 4-node clustering
Intel Xeon(r) E5-2697 v2 12-core processor single server
AMD Opteron(tm) 6284 SE 16-core processor single server

We always welcome highly motivated applicants to join the group. The applicants can be not only nuclear engineers but also somebody having majorities in mathematics, physics, and computer sciences who have interests in computer simulation and programming.
If you have interest in the application, please send me an email to hongsergi@hanyang.ac.kr