Responsible for identifying, analysing, and implementing improvements in reactor models and other simulation modules for full-scope simulators in operation. The work is carried out in close collaboration with multidisciplinary teams to ensure that the simulators meet demanding standards for technical accuracy, pedagogical quality, and operational reliability.

Developed training material in fundamental nuclear engineering subjects, with particular emphasis on thermodynamics. Structured, formulated, and visualised content covering thermodynamic principles, component functions (turbines, pumps, heat exchangers, condensers), and thermodynamic cycles for BWRX-300. The material was designed for global use in digital learning environments.

Created KSUSimLAB — a library of stand-alone part-scope simulators for advanced training of nuclear specialists, based on Python and Jupyter Notebooks. Conducted refresher training for instructors in reactor design, reactor physics, thermal hydraulics, and KSUSimLAB applications.

Responsible for technical adaptation, operational use, support, and further development of the BWRX-300 Desktop Simulator environment for use in the global training programme.

Certified to develop and implement the global training programme for BWRX-300 and to serve as responsible lead for the BWRX-300 Desktop Simulator in Sweden. Work included content development, technical adaptation, and operational support.

Expanded the simulation capabilities of the R3 full-scope simulator by implementing automated severe accident simulation. Developed scenarios for validation of Severe Accident Management Guidelines (SAMG) in collaboration with RAB’s severe accident response organisation and Westinghouse.

Upgraded the F1 full-scope simulator with a new core cycle based on F1C44. Implemented updated neutronic data and adapted the reactor model to represent cycle-specific core characteristics with high precision.

Reviewed and revised a digital training module in reactor physics to ensure technical accuracy, pedagogical structure, and usability.

Conducted a benchmarking study of RELAP5-HD (KSU) and TRACE (RAB) against actual measured data from a reactor trip in R3. Identified key mechanisms in steam generator dynamics and implemented model improvements in the full-scope simulator.

Developed advanced simulation models for severe accident sequences in the R3 full-scope simulator and in the stand-alone accident simulator (R3-HSIM-F), based on MAAP 5.05 in SimExec. Responsible for requirements definition, functional design, testing, and conceptual design of RDV-2, a modern generic visualization tool for simulation data from different models and simulator platforms.

Upgraded the core model in the F3 full-scope simulator to the CA11 equilibrium core with ATRIUM-11 fuel configuration. Implemented updated neutronic data for correct simulator behaviour during the applicable operating cycle.

Improved the accuracy of the reactor physics and thermal hydraulic models in the D53 full-scope simulator (Borssele Nuclear Power Plant, the Netherlands), increasing realism during normal operation, transients, and accidents.

Designed the 3D reactor model for the F12 full-scope simulator using RELAP5-HD, S3R, and SIMULATE-3 in order to accurately reproduce reactor dynamics during normal operation, transients, and accident scenarios.

Developed a new generation of automated verification and validation functions (Automated V&V) for efficient and reliable verification against requirements specifications, ANSI standards, and plant data.

Developed an advanced 3D reactor model for O3 using RELAP5-HD, S3R, and SIMULATE-3. The stand-alone O3 model was used for investigations including power spikes during restart of the 313 pump under power operation and the impact on level measurements during feedwater dilution disturbances, providing OKG with new insights and contributing to improved operational reliability.

Analysed why R4 operators had difficulty maintaining water level control in AREVA-designed steam generators during start-up. The study clarified the underlying mechanisms and resulted in a recommendation to use WR level measurement (Wide Range) as the primary indicator, which later led to implementation of an automated level control function.

Developed the 3D reactor model for R4 using 2×RELAP5-HD, S3R, and GARDEL/SIMULATE-3 for normal operation, transients, and accident dynamics.

Constructed the 3D reactor model for R3 using 2×RELAP5-HD, S3R, and GARDEL/SIMULATE-3 for normal operation, transients, and accident dynamics. The objective was to create a realistic and pedagogically effective simulator for operator training and safety analyses.

Implemented the Automated Scenario Testing (AST) verification and validation system in the full-scope simulators for R1, R3, and R4, enabling robust execution of ANSI standard tests and validation against transient data.

Developed training material and delivered a course for staff from the Swedish Radiation Safety Authority (SSM), focusing on dynamic system behaviour during normal operation, disturbances, and accidents in BWR and PWR plants.

Designed F12HSIM, a stand-alone severe accident simulator for Forsmark 1 and 2, based on MAAP 5.03 integrated in the SimExec environment. Used by FKA’s accident response organisation.

Trained Japanese engineers at ORDC in development of DesignEP and PSA-HD applications based on MAAP5.01 in SimExec for simulation of severe accidents.

Invented and developed MCS2SIM, an innovative method for integrating PSA results into full-scope simulators for deterministic analysis (DSA) of potential accident sequences. Piloted on R1 and subsequently applied to R1, R2, and R3 at Ringhals. The analyses were delivered to RAB.

Constructed the 3D reactor model for R2 using 2×RELAP5-HD, S3R, and GARDEL/SIMULATE-3. Integrated MAAP5 for severe accident simulation (HSIM-I).

Developed the 3D reactor model for O1 using RELAP5-HD, S3R, and SIMULATE-3 in SimExec-HDS. Also responsible for O1’s main process models (JTopmeret/SimExec).

Responsible for the very first BWR reactor model based on HDS technology (Advanced Modeling Team, GSE Systems, Baltimore). The model was built using RELAP5-HD, S3R, and SIMULATE-3 in SimExec, pioneering work that had not previously been carried out by anyone else.

Lead specialist for the design and implementation of reactor models for the Tokai-2 and Tsuruga-2 full-scope simulators using RELAP5-HD, REMARK, and MAAP4, in close collaboration with JAPC’s technical experts.

• Invented, developed, and implemented the algorithms for Real Data Viewer (RDV-1), which became the standard for visualization of reactor models in Swedish nuclear simulators
• Complete redesign of the O2 full-scope simulator (Rose/Orchid in SimExec) and modernisation of O3 within the PULS project (increase from 109% to 129% nominal power)
• Taught staff at Swedish nuclear power plants in reactor physics, thermodynamics, and thermal hydraulics (consultant to KSU)

• PSA safety analysis of Studsvik (R2 and R2-0) using FMEA, FTA, and ETA in RiskSpectrum (Studsvik AB)
• LISA safety analysis (Leningrad In-Depth Safety Assessment) — unit 2, LNPP, Russia (SKI)
• RELAP5 water hammer calculations for system 322 in O2 and Barsebäck-2 (OKG)
• LOCA analysis of system 313 in O2 — loads on the core shroud and reactor vessel (OKG)
• Design calculations for the O2 emergency core spray system (system 323) using RELAP5 (Westinghouse Electric Sweden)
• Validation of the ASTRID code against MAAP4 (SKI)
• Review and update of technical system descriptions for O3 (OKG)
• Independent review of STF changes, Chapter 4, O2 (OKG)
• Excel/VBA application for Impact Vector Analysis (common cause failures, CCF) within PSA work (SKI)
• Technical support for plant modernisation, Skellefteå Kraft AB
• Design of handling methods for low- and intermediate-level waste, Ignalina Nuclear Power Plant (SKI)
• Board member 2002–2004; responsible for IT (servers, VPN, firewalls)

• Adapted the ARROTTA neutronics code to RBMK reactor physics; created a specialized neutron cross-section library using CASMO, WIMS, and HELIOS, enabling the first Western computational code application to RBMK reactors
• Analysed hypothetical incidents and severe event sequences in RBMK reactors
• Analysed new fuel containing the erbium isotope ¹⁶⁷Er to reduce the positive steam void coefficient (CASMO, HELIOS)
• Developed an analytical calculation model for the Accident Localization System (ALS) in the RBMK-1500 at Ignalina