Structural and Thermal-Fluids Engineering

Nuclear Services/Systems and Equipment Engineering. Hydraulic and thermal analyses for design of nuclear power plant fluid systems. Design and design modification analyses for Emergency Core Cooling System (ECCS) piping and components for existing Combustion Engineering (CE) Pressurized Water Reactors (PWRs). Reactor Coolant System (RCS) design analyses to support flow and differential pressure estimation, flow balancing, and Reactor Coolant Pump (RCP) design and operational limits for new AP1000 and existing CE PWRs. Thermosiphoning analyses for Control Rod/Element Drive Mechanisms (CRDMs/CEDMs) for both Westinghouse and CE PWRs to support Reactor Vessel Head (RVH) replacement projects. Diverse and Flexible Coping Strategies (FLEX) related documentation for CE and Westinghouse PWRs in the US, including Overall Integrated Plan (OIP) development and hydraulic modeling of FLEX modifications. Support for fluid systems-related emergent/outage issues for CE fleet, including Justification for Continued Operation (JCO) documentation. Response to U.S. Nuclear Regulatory Commission (NRC) Requests for Additional Information (RAIs). Oversight of long term chemical addition pump testing at nuclear plant site and at the pump manufacturer's facility. Serve as on-site integrator between design and manufacturing teams for several post-Fukushima related fluid system products at Westinghouse Nuclear Components manufacturing facility in Newington, NH.

Compiled Level III schedule for design of mechanical systems related to Calvert Cliffs Unit 3.

Design and manufacturing of water filtration systems for industrial applications (mainly cooling towers). Constructed solenoid panels, wired solenoids and motor starters to control boxes, rebuilt pumps, reprogrammed Programmable Logic Controllers (PLCs), made owner's manuals for filtration systems, wrote engineering submittals, created system drawings in AutoCAD, and performed service work on operational systems.