Nuclear Engineer and Researcher with 20 years of experience in nuclear power plant engineering. Extensive experience and in-depth knowledge in power plant design, reactor safety, nuclear regulation, safety analysis, and non-LWR design and licensing. Areas of expertise in nuclear power reactors include:
- Nuclear power plant design
- Safety analysis
- Nuclear regulation and licensing (Parts 50 and 52, LWRs and Non-LWR)
- Nuclear computer codes, i.e., TRACE, RELAP, COBRA, MCNP, MACCS
Providing technical consultation and training to foreign nuclear regulators in developing their country-specific regulatory documents and processes and in training their staff members in reactor siting, reactor safety, nuclear regulation, safety analysis, and regulatory review; a member of a team maintaining NRC safety codes, i.e., TRACE, RELAP, reviewed TRACE code updates, conducted code assessment; developed TRACE models for the integral test and separate effect facilities; involved in developing several training courses for NRC staff, i.e., mechanical codes and standards, fundamentals of reactor licensing (FORL), fundamentals of reactor technical review (FORTR), reactive inspections, and reactor inspection leadership training (RILT); following the Fukushima accident, supported the staff in developing for the Commission a report entitled, "A comparison of U.S. and Japanese regulatory requirements in effect at the time of the Fukushima accident ".
Provided technical support to DOE’s Generation IV and NGNP programs: reviewed different advanced design concepts and studied the issues related to licensing next generation reactors; reviewed all technical provisions in 10 CFR 50 with respect to their applicability of 10 CFR 50 regulations to non-LWRs; drafted a white paper exploring NGNP licensing strategies with within the current NRC regulatory regime and future risk-informed technical neutral framework, and discussing pros and cons associated with each strategies. One principal contributor to a report entitled " Advanced Nuclear Technology Evaluation Criteria" for DOE NE. Participated in a pre-conceptual study of a remote treatment plant in the DOE complex for processing and disposal of legacy metal reactor spent fuel.
Provided technical consulting service to an LMR vendor, reviewing its conceptual design for conformance with international standards, identifying potential licensing issues, developing strategies for resolving the identified issues, and assisting the vendor in identifying design basis and beyond design basis events. Reviewed the design information of the LMR in several areas (i.e., reactor system and connected systems, accident analysis, PRA) to identify information gaps to support licensing; and reviewed and integrated the reviews of the team members in other areas to create the final technical report for the vendor.
Performed severe accident consequence analysis in support of the TVA's Clinch River ESP application, developing WinMACCS models, calculation notebook, and analysis of the results going into the application; hands-on experience with WinMACCS code; familiar with NRC 10 CFR Part 51
Conducted research projects related to advanced reactor control concepts (i.e.,design, implementation, and testing on a research reactor), BWR core stability, experimental and numerical study of the instability phenomena in a two-phase natural circulation test facility; designed and optimized a low-energy gamma source (Hg 203) employed in an NDT instrument; using the MCNP code, modeled the neutron irradiation of Hg 202 samples in a test reactor.
Involved mainly in design of Chinese Standard 600MW NPP, i.e., safety systems design, equipment specifications, equipment and piping layout in the containment; also involved in the feasibility study of building a Russian VVER-1000 NPP at a proposed site in China.
The Pennsylvania State University, MS In Nuclear Engineering, 2001
Harbin Shipbuilding Engineering Institute (now Harbin Engineering University, Harbin, China), BS In Nuclear Engineering, 1993