OOIR: Observatory of International Research

Papers

(The H4-Index of Nuclear Engineering and Design is 23. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2020-11-01 to 2024-11-01.)

Article	Citations
A review of research and development of supercritical carbon dioxide Brayton cycle technology in nuclear engineering applications	131
Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor	50
Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor	41
Physics-informed reinforcement learning optimization of nuclear assembly design	37
Preliminary design of the suppressive containment system based on HPR1000	37
Dynamic modelling, simulation, and control design of a pressurized water-type nuclear power plant	35
High-energy surface processing of zirconium alloys for fuel claddings of water-cooled nuclear reactors	34
ALFRED reactor coolant system design	34
Source localization on large-scale canisters for used nuclear fuel storage using optimal number of acoustic emission sensors	33
Burnable absorbers in nuclear reactors – A review	32
A new thermal analysis model with three heat conduction layers in the nuclear waste repository	31
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), phase 2 – Results of severe accident analyses for unit 2	30
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) Phase 2 – Results of severe accident analyses for Unit 1	29
A comprehensive survey of inverse uncertainty quantification of physical model parameters in nuclear system thermal–hydraulics codes	28
Review of molten salt reactor off-gas management considerations	28
Neutronics, thermal-hydraulics, and multi-physics benchmark models for a generic pebble-bed fluoride-salt-cooled high temperature reactor (FHR)	25
Transfer learning with limited labeled data for fault diagnosis in nuclear power plants	25
Core power control of the ADS based on genetic algorithm tuning PID controller	25
Full core LOCA safety analysis for a PWR containing high burnup fuel	24
A review of recent advances in HTGR CFD and thermal fluid analysis	24
Ageing and air leakage assessment of a nuclear reactor containment mock-up: VERCORS 2nd benchmark	24
On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives	23
Thermodynamic design and Off-design investigation of nuclear power supercritical CO2 recompression cycle	23