Lead Engineer, Thermal Hydraulic Analyses

Job Description Summary

This role is instrumental in advancing our nuclear thermal-hydraulic capabilities, particularly in supporting fuel development and its associated subchannel and system codes. The position requires a dynamic thermal-hydraulic engineer skilled in core and fuel thermal-hydraulic analysis and methods development. Key responsibilities include the development and optimization of fuel design and performance, advancing thermal-hydraulic methodologies, including bundle critical power and pressure drop.

This role is part of the Thermal & Fluids Analysis team, which oversees the development, maintenance, and technical consultation of thermal-hydraulic computer codes, correlations, and methodologies pertinent to Boiling Water Reactors (BWR), Pressurized Water Reactors (PWR), and advanced/fast reactors, including their fuel systems. The team plays a crucial role in ensuring the accuracy and reliability of analytical tools and methods that support reactor performance and safety evaluations.


Job Description


Essential Responsibilities

• Lead the technical development, accuracy, and uncertainty qualification, testing, verification, and maintenance of analytical methods for evaluating steady-state and transient core/fuel performance.
• Develop single-phase and two-phase thermal-hydraulic test plans, interface with test personnel related to all testing activities, perform associated data analysis, and develop empirical correlations or mechanistic models.
• Work with nuclear and mechanical engineering teams in the development of new fuel products / software in the area of thermal hydraulics.
• Work within a regulatory framework for nuclear software quality assurance for engineering programs.
• Prepare, document, and present technical data to both internal and external customers.
• Enhance team processes to drive efficiency and simplification.
• Communicate effectively with method users through support, documentation, and training.
• Ensure high-quality work in compliance with NRC regulations, customer requirements, and business quality standards.
• Foster a team culture rooted in teamwork, integrity, transparency, and accountability.
• Collaborate with team members globally across various time zones.
• Interface with regulatory agencies (NRC, DOE, etc.) as necessary.
• Strong interpersonal skills and demonstrated ability to work in a team.
• Displays a strong drive for continuous improvement.
• Displays an engaging, can-do, optimistic attitude.
• Excellent oral and written communication skills.
• Strong analytical capabilities, problem solving skills, and process skills.

Required Qualifications

• Bachelors degree from an accredited university or college in nuclear engineering, mechanical engineering, physics, computational methods or a closely related technical discipline with a thesis or substantial coursework with thermal-hydraulics and two-phase flow.
• 5 years of experience in a regulated nuclear engineering environment, with a specific focus on thermal-hydraulic codes, two-phase flow analysis, or reactor safety methodologies

Eligibility Requirements

• The preferred work location for this role is at the GVH Headquarters in Wilmington, NC; but highly qualified (US based) remote candidates will be considered.
• Comfortable with less than 10% travel.
• This role requires access to U.S. export-controlled information. If applicable, final offers will be contingent on ability to obtain authorization for access to U.S. export-controlled information from the U.S. Government.

Desired Qualifications

• Master's Degree with 2 years of experience in thermal hydraulics.
• Understanding on experimental and analytic aspects of two-phase flow fundamentals and two-phase flow phenomena during BWR and PWR steady-state operations, transients, and accidents (e.g., void fraction, two-phase pressure drop, two-phase flow regime transition, boiling and condensation heat transfer, critical heat flux or annular film dry out, post boiling transition heat transfer, rewet, counter-current flow limitation, critical flow, flow instability, and the drift-flux model/two-fluid model for two-phase flow analysis).
• Experimental background in two-phase flow.
• Experience with thermal-hydraulic…