Crud Related Risk Assessment Methodology Development under PWR Conditions
| Event Date: | August 28, 2024 |
|---|---|
| Speaker: | Dr. Guoqiang Wang
ASME Fellow |
| Speaker Affiliation: | Pacific Northwest National Laboratory |
| Type: | In-person |
| Time: | 3:30 pm |
| Location: | MATH 175 |
| Priority: | No |
| School or Program: | Nuclear Engineering |
| College Calendar: | Hide |
Abstract:
This presentation introduces a laboratory test program to measure simulated fuel deposit thermal conductivity under a variety of conditions experienced in a PWR fuel
assembly. This thermal conductivity information is necessary to allow more accurate predictions of fuel rod surface known as crud. Surface temperature predictions are in turn needed to improve the nuclear industry’s ability to determine margin to potential cladding failure due to crud induced localized corrosion (CILC). This presentation also summarizes the crud related challenges in the nuclear industry, including CILC and crud induced power shift (CIPS). Crud related model development and applications as well as advanced CIPS/CILC method development will be presented. Future work, including relevant accident tolerant fuel (ATF) development, testing and benefits are included at the end of the presentation slides. Accordingly, a few next steps are proposed.
Bio:
Guoqiang Wang, ASME Fellow, is a chief engineer at National Security Directorate in Pacific Northwest National Laboratory (PNNL). Before his current role, Dr. Wang was a Consulting Engineer in the Methods and Technology Department of Westinghouse. He had worked for Westinghouse Electric Company LLC for 23 years. Dr. Wang has had 36 years of proven performance in the nuclear industry internationally. Dr. Wang had worked as a technical expert in the fields of TH, advanced fuel development, safety analysis as well as ATF and CHF TH testing at simulated PWR chemistry and operating conditions. He led and set up a cold spray unit in 2018.
Dr. Wang is a member of the ASME Nuclear Engineering Division (NED) executive committee and a contributing member of ASME Board on Nuclear Codes and Standards (BNCS). Dr. Wang received his Bachelor of Science Degree in Reactor Engineering in Tsinghua University in 1988. He received his Doctoral Degree and concurrent MS Degrees in the Department of Mechanical and Nuclear Engineering at PSU, respectively.
2024-08-28 15:30:00 2024-08-28 16:30:00 America/Indiana/Indianapolis Crud Related Risk Assessment Methodology Development under PWR Conditions MATH 175