At PSI, you research advanced models for droplet behaviour in pressurised water reactors. You help develop safer nuclear technologies and join a team focused on innovative, interdisciplinary collaboration.
Your tasks
- Develop advanced closure models for droplet breakup on wet and dry spacer grids in pressurised water reactors
- Implement, test and validate mechanistic droplet breakup models for wet spacer grids
- Create physics-based correlations for droplet size distributions in PWR fuel assemblies during reflood
- Integrate and test droplet behaviour models in the US-NRC’s system thermal-hydraulics code TRACE
- Perform sensitivity and uncertainty analyses of the new models
- Prepare technical reports and publish scientific results at international conferences and in peer-reviewed journals
- Take part in teaching activities with guidance from your thesis advisor
What you bring
- Master’s degree or equivalent in nuclear or mechanical engineering, physics or applied mathematics
- Strong background in nuclear engineering, especially two-phase thermal hydraulics
- Experience using system or subchannel thermal-hydraulics code and CFD simulation codes, ideally TRACE
- Programming skills in FORTRAN and scripting languages like Python
- Familiarity with uncertainty quantification and sensitivity analysis methods (such as BEPU, CSAU) is a plus
- Fluent spoken and written English; German proficiency is beneficial
What we offer
- Work in an interdisciplinary, innovative and dynamic environment
- Receive systematic training on the job and personal development opportunities
- Benefit from a strong vocational training culture
- Modern employment conditions and on-site infrastructure support work-life balance
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Über uns
PSI is Switzerland’s largest research institute for natural and engineering sciences. We focus on future technologies, energy, climate, health, and the fundamentals of nature. We offer a collaborative culture, modern facilities, and support for your professional growth.
Das Team
The Laboratory for Reactor Physics and Thermal-hydraulics conducts computational and experimental research on nuclear reactor safety, especially for Light Water Reactors and Swiss nuclear power plants.