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Introduction

The International Congress on Advances in Nuclear Power Plants (ICAPP) is cosponsored by the American Nuclear Society, the Atomic Energy Society of Japan, the Korea Nuclear Society, the French Nuclear Society, and a number of major international nuclear societies. The meeting’s annual host location cycles through the U.S., Europe, and Asia, giving it its global flair.ICAPP provides a forum for nuclear industry leaders to exchange information, present results from their work, review the state of the industry, and discuss future directions and needs for the deployment of new nuclear power plant systems.Uniting the business and technical interests of participants and exhibitors, ICAPP attracts 300+ specialists from around the world, offers more than 250 scientific/technical presentations in plenary and parallel sessions, and features additional panel and discussion sessions. The American Nuclear Society, as host for 2018, invites you to join us for this unique event.

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TECHNICAL TRACKS1. WATER-COOLED REACTOR PROGRAMS AND ISSUESEvolutionary designs, innovative, passive, light and heavy water cooled reactors; super critical water reactors; 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.2. HIGH TEMPERATURE REACTORSDesign and development issues, components andmaterials, 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.3. ADVANCED REACTORSReactor technology with enhanced fuel cycle features for improved resource utilization, waste characteristics, and power conversion capabilities. Small Modular Reactor (SMR) development and licensing; potential reactor designs with longer development times such as liquid fuel reactors, Gen IV, INPRO, and GNEP.4. OPERATION, PERFORMANCE AND RELIABILITY MANAGEMENTReactor technology with enhanced fuel cycle features for 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.5. PLANT SAFETY ASSESSMENT, REGULATORY ANDLICENSING ISSUESTransient and accident performance including LOCAand 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 nonradiological 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.6. REACTOR PHYSICS AND ANALYSISNuclear 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 (i.e. pebbled bed generation reactors) and characterization of spent fuels.7. THERMAL HYDRAULICS ANALYSIS AND TESTINGExperimental 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.8. FUEL CYCLE AND WASTE MANAGEMENTTRU separation processes, fuel and target design for transmutation, performances, scenarios for P&T deployment, review of national programs on P&T, impact of P&T on waste minimization, 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), Fuel supply and waste management and non-proliferation concerns9. MATERIALS AND STRUCTURAL ISSUESFuel, 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.10. NUCLEAR ENERGY AND GLOBAL ENVIRONMENTEnvironmental 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, and its qualitative contribution. International collaborative arrangement to support world nuclear energy development, especially in developing countries and with respect to fuel supplyand waste management and non-proliferation concerns.

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Important Date
  • Conference Date

    Apr 08

    2018

    to

    Apr 11

    2018

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