- Retraction notice to “Superior techniques for disposal of highly radioactive waste (HLW)” [Progress in Nuclear Energy 59, (2012), 75-85]
- Corrigendum to ‘Onsite power system risk assessment for nuclear power plants considering components ageing’ Progress in Nuclear Energy Volume 110 (2019) 384–392
- Corrigendum to “Simplified two-group two-fluid model for three-dimensional two-phase flow computational fluid dynamics for vertical upward flow” [Prog. Nucl. Energy 108 (2018) 503–516]
- [sciencedirect.com] Corrigendum to “Possible use of bisphenol-a polycarbonate in radioactive waste embedding” [Prog. Nucl. Energy 90C (2016) 98–104]
- Retraction notice to “Subchannel Analysis of TiO2 Nanofluid as the Coolant in VVER-1000 Reactor” Progress in Nuclear Energy 73, (2014), 140-152
- CAREM project: Innovative small PWR
- Corrigendum to “An experimental study of pool entrainment in high gas flux region” [Prog. Nucl. Energy 89C (2016) 191–196]
- Corrigendum to “Evaluation of candidate materials for SCWR turbine and balance of plant shielding” [Prog. Nucl. Energy, 79, 136–141]
- Operation and control of reactors
- Source papers in reactor noise
- Vapor explosions in light water reactors: A review of theory and modeling
- An overview of radiation effects on electronic devices under severe accident conditions in NPPs, rad-hardened design techniques and simulation tools
- Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator tubes in Nuclear Power Plants
- [sciencedirect.com] PWR steel pressure vessel design and practice
- A review of separation processes proposed for advanced fuel cycles based on technology readiness level assessments
- Radioactive releases from nuclear installations
- A world's dilemma ‘upon which the sun never sets’: The nuclear waste management strategy (part II): Russia, Asia and the Southern Hemisphere
- Nuclear heat for hydrogen production: Coupling a very high/high temperature reactor to a hydrogen production plant
- Noise investigations in boiling-water and pressurized-water reactors
- A review of ground-based robotic systems for the characterization of nuclear environments
- Clay as a barrier to radionuclide migration
- Performance assessment models for low level radioactive waste disposal facilities: A review
- A review of the cognitive basis for human reliability analysis
- The use of ionising radiation to image nuclear fuel: A review
- Flow-induced vibration in nuclear reactors: A review
- Technology perspectives from 1950 to 2100 and policy implications for the global nuclear power industry
- Vertical upward two-phase flow CFD using interfacial area transport equation
- Integrated Risk-Informed Design (I-RID) methodological framework and computational application for FLEX equipment storage buildings of Nuclear Power Plants
- A world's dilemma ‘upon which the sun never sets’ – The nuclear waste management strategy (part I): Western European Nation States and the United States of America
- Review of sub-channel code development for pressurized water reactor and introduction of CORTH-V2.0 sub-channel code
- Review on scope of metallic alloys in gamma rays shield designing
- Review of research on flow instabilities in natural circulation boiling systems
- Relative biological effectiveness of neutron radiation and its implications for quality factor and dose limitation
- Current achievements on bubble dynamics analysis using MPS method
- Design concepts of supercritical water-cooled reactor (SCWR) and nuclear marine vessel: A review
- Overview of recent experimental works on high energy neutron shielding
- Transport equations in moving material Part I: Neutrons and photons
- Two-person game model of long-term safeguards for a final repository for spent nuclear fuel
- Soft computing technologies in nuclear engineering applications
- An exploration of the relationship between nuclear decommissioning projects characteristics and cost performance
- PWR heat exchanger tube defects: Trends, signatures and diagnostic techniques
- An experimental investigation on the effects of barite/hematite on the radiation shielding properties of serpentine concretes
- Theory and implementation of nuclear safety system codes – Part II: System code closure relations, validation, and limitations
- Developments of analyses on grid-to-rod fretting problems in pressurized water reactors
- Life prediction techniques for combined creep and fatigue
- Stakeholder perspectives on the cost requirements of Small Modular Reactors
- Climate change vulnerability assessment for the uranium supply chain in Australia
- Thermodynamic properties of actinides and fission products in liquid bismuth
- The influences of maximum aggregate size and cement content on the mechanical and radiation shielding characteristics of heavyweight concrete
- Natural convection heat transfer in corium pools: A review work of experimental studies
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