The Sr. DSA Engineer will be responsible for developing methods and performing analyses to demonstrate that the SMR-300 satisfies its safety and licensing requirements. These types of analyses include evaluations of the reactor core, reactor coolant system, engineered safety features, containment, and radiological releases associated with anticipated operational occurrences (AOOs) and design basis accidents (DBAs). Additionally, the DSA group is responsible for the development, verification, and validation of the computer codes used in these analyses.

Location: Almondsbury, UK; Madrid, Spain

• Perform deterministic safety analyses for Anticipated Operational Occurrences (AOOs) and Design Basis Accidents (DBAs) to support the licensing and design of the SMR-300 reactor.
• Evaluate reactor core behavior, reactor coolant system performance, engineered safety features, containment response, and radiological consequences under normal and accident conditions.
• Develop, apply, and maintain analytical methods and models used in safety analysis.
• Conduct thermal-hydraulic, neutronic, and systems-level simulations to demonstrate compliance with regulatory safety criteria.
• Prepare technical reports and contribute to licensing documentation, including Safety Analysis Reports (SAR/FSAR) and regulatory submittals.
• Support interactions with regulatory bodies (e.g., NRC), including responses to requests for additional information (RAIs).
• Participate in the development, verification, and validation (V&V) of safety analysis computer codes and tools.
• Collaborate with multidisciplinary engineering teams to ensure design solutions meet safety and licensing requirements.
• Review and provide technical guidance on analyses performed by junior engineers.
• Ensure all work is performed in accordance with quality assurance standards and applicable industry regulations.

• B.S degree in nuclear engineering, mechanical engineering, or closely related field from an accredited college or university
• Familiarity with thermal-hydraulic behavior of light water reactors (LWRs)
• Familiarity with industry computer codes such as RELAP5, RETRAN, COBRA, VIPRE, GOTHIC, etc.
• At least 10 years' experience developing and/or using codes and methods associated with LWR safety analysis calculations
• Comprehensive knowledge of U.S. NRC regulations pertaining to LWR safety analyses including code validation
• Familiar with NQA-1 software quality assurance programs
• Experience with programming languages such as FORTRAN, C++, or Python
• Excellent technical writing, interpersonal, and communication skills
• Eligible to work under 10 CFR Part 810