Brian of Westinghouse Electric Company

Addressing aging of the nuclear reactor pressure vessel (RPV) to ensure safe long-term operation of the PWR fleet.

The US nuclear fleet of 93 power reactors produce 20% of the electricity in the US. As these plants continue to operate, it is important to ensure that aging issues are properly monitored and addressed. The RPV fracture toughness is affected by high energy impact of neutrons from the core. Monitoring programs and improved methods of understanding of and testing for fracture toughness will be discussed along with current efforts.

Biography:

J. Brian Hall, Fellow Engineer, Westinghouse, M.S., Engineering Mechanics, Pennsylvania State University, 1990

Brian has unique experience in the nuclear power industry gained over the last 30+ years, enabling him to understand the interrelationship between material mechanical behavior, fracture mechanics, and aging/embrittlement.  Brian’s experience includes: material specifications for component replacement and new plants, failure analysis, materials testing, fracture mechanics, and material aging evaluations for uprates, repairs and license renewal for nuclear power plants.  His contributions have been in the areas of reactor pressure vessel (RPV) integrity, RPV internals aging, and other reactor coolant system materials. He has supported materials reliability programs for individual utilities, the Pressurized Water Reactor Owners Group Materials Committee, and the Electric Power Research Institute (EPRI).  He is the chair of the ASTM E10.02 Subcommittee, “Behavior and Use of Nuclear Structural Materials,” which is responsible for standards related to RPV embrittlement surveillance, and is the chair of ASTM E10 Committee, “Nuclear Technology and Applications.”  Through publications and leadership in industry activities, he is recognized internationally.  He has advanced the use of the master curve method (direct fracture toughness) for the benefit of the utilities operating pressurized water reactors, improved operation and enabling operation beyond 80 years.

Jeff of Westinghouse Electric Company

The eVinci™ microreactor uses alkali metal (sodium) heat pipes configured within a core block to transfer heat from the reactor core to a heat exchanger. Heat pipe thermal performance is critical for thermal to electrical power conversion efficiency. This presentation summarizes initial testing and development of an Eddy-Current Flow Meter (ECFM) to support heat pipe thermal performance evaluations and investigate the feasibility of active sodium flow monitoring in an eVinci™ style microreactor.

Biography:

Jeff Arndt will provide a brief introduction of the Eddy Current Flow Meter (ECFM) for eVinci.

Georgia of Westinghouse Electric Company

The eVinci™ microreactor uses alkali metal (sodium) heat pipes configured within a core block to transfer heat from the reactor core to a heat exchanger. Heat pipe thermal performance is critical for thermal to electrical power conversion efficiency. This presentation summarizes initial testing and development of an Eddy-Current Flow Meter (ECFM) to support heat pipe thermal performance evaluations and investigate the feasibility of active sodium flow monitoring in an eVinci™ style microreactor.

Biography:

Georgia Clifford will elaborate on the details of the current testing of the Eddy Current Flow Meter (ECFM) for eVinci.