Evolutionary designs, innovative, passive, light and heavy water cooled reactors development of SMRs issues related to meeting near term utility needs; emerging plant safety issues, design improvements business, political and economic challenges; infrastructure limitations and improved construction techniques including modularization.

Emerging reactor technology with molten salt as circulating nuclear fuel (MSR). Design and development issues, components and materials, safety and reliability, economics, demonstration plants and environmental issues.

Design and development issues, components and materials, safety, reliability, economics, demonstration plants and environmental issues, fuel design and reliability, power conversion technology, impact of non electricity applications on reactor design; advanced thermal and fast HTR designs.

Reactor technology with enhanced fuel cycle features for improved resource utilization, actinide management, and waste minimization capabilities. Potential reactor designs with longer development times for increased sustainability. Other Gen IV reactor designs with longer development times and enhanced capabilities compared to Light Water Reactors.

Environmental impacts and carbon reduction of nuclear and alternative systems, including applications such as the production of hydrogen, sea water desalination, liquid fuels produced with reduced carbon footprints, biofuels, heating and other co-generation applications. Scenario analysis of nuclear role substitution for fossil fuels not only for power but for transportation, industrial process heat and its qualitative contribution.

Training, O&M costs, life cycle management, risk based maintenance, operational experiences performance and reliability improvements, outage optimization, human factors, plant staffing, outage reduction features, major component reliability, repair and replacement, in-service inspection, and codes standards.

Transient and accident performance including LOCA and non LOCA, severe accident analysis, nuclear plant security, natural disaster initiated severe accidents, impact of risk informed changes, accident management and emergency situations, advances in regulatory issues for operating and future plants, life assessment and management of aging, degradation and damage extension lessons from plant operations, containment with radiological and non-radiological inventory, probabilistic safety assessment and reliability engineering, new methodologies for plant safety analysis. Fire protection, emergency preparedness, and used fuel storage and transportation. Reactor licensing, advanced reactor design certification, combined license, and multinational design license application and evaluation.

Nuclear data libraries and related error files, lattice calculation, deterministic and Monte Carlo approaches, core calculation, multi physics coupling. Progresses achieved in this domain contribute to the improvement of core performances (for existing reactors and next generation reactors). New fuels, new fuel management, new reactor cores and characterization of spent fuels.

Experimental techniques and measurements, phenomena identification and ranking, computer code scaling applicability and uncertainty, containment thermal hydraulics, separate and integral effect tests, improved code development and qualification, single and two phase flow heat transfer, advanced computational thermal hydraulic methods; single and two phase CFD.

Fuel cycle sustainability, fuel cycle options, review of national programs on advanced fuel cycle options including P&T, advanced reprocessing processes and technologies (Purex Coex, Urex, Pyro), nuclear material recycling technologies (MIMAS, Vibropack), modeling of processes, back end fuel cycle options, uranium and plutonium management issues, waste conditioning storage and disposal, thorium cycle, fully integrated fuel cycle and symbiotic nuclear power systems, Accelerator Driven Systems (ADS), and non-proliferation concerns.

Fuel, core, reactor pressure vessel and internals structures, advanced materials issues, environmental effects and fracture mechanics, concrete and steel containments design and analysis, design and monitoring for seismic, dynamic and extreme accidents, irradiation issues, materials and structural mechanics issues, aging material issues, codes and standards for new generation plants.

The purpose of the Student Program is to encourage the active participation of students in ICAPP 2023 by submitting high quality technical papers on the various aspects of the advances in nuclear power plants.

This program seeks to promote the interaction of students with experienced nuclear professionals and to help them establish mentoring and networking links in their areas of interest.

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After reviewing all applied abstracts by the Technical Program Committee, 20 papers will be shortlisted for a final presentation at the Student Competition session, and best 10 presentations will be awarded at a ceremony during the congress.