Perform deterministic (DBA/BDBA) and/or probabilistic (PSA/PRA) safety analyses for the assessment of reactor systems and safety functions.
Contribute to safety analyses covering normal operating conditions, transient conditions, Design Basis Accidents (DBA), and Beyond Design Basis Accidents (BDBA)/Design Extension Conditions (DEC).
Perform or support analysis and modeling activities to assess the thermal-hydraulic behavior of reactor systems.
Perform or support system thermal-hydraulic, accident, and/or severe accident analyses using nuclear safety analysis codes.
Perform or support model development, analysis, quantification, and results evaluation for Level 1, Level 2, and, where applicable, Level 3 PSA/PRA studies.
Evaluate results obtained from DBA/BDBA and thermal-hydraulic analyses and establish their linkage with the relevant PSA/PRA risk models.
Contribute to event tree, fault tree, dependency, human reliability, and risk quantification activities.
Perform or support analyses related to core damage, fuel damage, radioactive material release, and containment integrity.
Technically evaluate PSA results and correlate analysis findings with design features, safety functions, safety requirements, and regulatory criteria.
Contribute to the development, verification, validation, updating, and quality control of analysis models, as well as the technical evaluation of analysis results.
Prepare technical analysis reports, calculation documents, model documentation, and safety assessment documents.
Coordinate with multidisciplinary engineering teams and effectively communicate analysis results to relevant design and nuclear safety activities.
REQUIRED QUALIFICATIONS
Professional experience in at least one of the following areas within the nuclear industry: PSA/PRA, DBA/BDBA, deterministic safety analysis, or nuclear thermal-hydraulics.
Working knowledge of the systems, safety features, and thermal-hydraulic behavior of LWR/PWR reactors.
Hands-on experience in at least one of the following areas:
PSA/PRA modeling and quantification
DBA/BDBA and accident analysis
System thermal-hydraulic analysis
Severe accident analysis
Knowledge of event tree analysis, fault tree analysis, dependency modeling, human reliability analysis (HRA), and risk quantification within PSA/PRA studies.
Knowledge of accident scenarios, transient behavior, system response, and safety acceptance criteria within deterministic safety analysis.
Experience with at least one of the following PSA/PRA tools:
CAFTA
SAPHIRE
RiskSpectrum
Or equivalent PSA/PRA software
Experience with at least one of the following nuclear safety analysis codes:
RELAP5-3D
TRACE
MELCOR
Or equivalent thermal-hydraulic/severe accident analysis codes
Working knowledge of ASME/ANS PRA Standards and relevant NRC and/or IAEA safety analysis and risk assessment documents.
Strong written communication skills, with the ability to prepare technical reports and analysis documentation.
Sufficient English proficiency to read, understand, interpret, and work with technical documents.
Strong analytical and problem-solving skills.
Ability to work effectively within multidisciplinary engineering teams.
PREFERRED QUALIFICATIONS
Experience in PSA/PRA and/or DBA/BDBA for PWR, SMR, or similar nuclear reactor designs.
Experience in the interaction and integration between PSA/PRA and deterministic safety analyses.