Nuclear Power Plant Design and Analysis Codes

- Development, Validation, and Application

Forfatter: info mangler
Bog
  • Format
  • Bog, paperback
  • Engelsk

Beskrivelse

Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs.

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Detaljer
  • SprogEngelsk
  • Sidetal608
  • Udgivelsesdato13-11-2020
  • ISBN139780128181904
  • Forlag Woodhead Publishing
  • FormatPaperback
Størrelse og vægt
  • Vægt1260 g
  • coffee cup img
    10 cm
    book img
    19,1 cm
    23,5 cm

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    Sam Accident Multiphase flow Nuclear power plants Thermal analysis Machine learning Regulation Monte-Carlo Moose Multiscale modeling Artificial intelligence Thermal hydraulics Free surface flow MCCI Nuclear Power Plant AC Heat transfer coefficient Thermal hydraulic Heat transfer Cybersecurity MPS Nuclear Thermal-Hydraulics Pressure Drop Multiphysics Athlet Software quality assurance Reactor Radiation damage Lattice Boltzmann method Assessments Coupling Sampson Germinal Neutron irradiation Artificial neural network Trace Transient Analysis Expert system Cyberattack Nuclear Safety Computational codes ONB VV Boiling CASL 3D module Advanced reactor ALCYONE Assemblies codes ALFRED reactor ATHLET-CD Code for nuclear power BPN Code development Critical Heat Flux Coupled codes CTF Boiling Curve Ex-vessel Deterministic method Engineering level system code Entry-level guidance Code introductions Fuel performance codes Color-gradient model COCOSYS Fuel codes Fission product behavior Core degradation FRAPCON FRAPTRAN In situ decommissioning (ISD) Sensor Network Test Bed Leak rate in-vessel Flow mixing Mechanism-based codes MELCOR Melt jet breakup Frequent episode OpenMC NURESAFE GNN Pressurizer Pseudopotential model Software development life cycle Severe Accident Temporal data mining (TDM) TRANSURANUS TRANSURANUS burn-up module In-pile models Source Code Subchannel analysis Neutronics modeling of nuclear reactors Thermal-hydraulics codes Particle method System-level code TRANSURANUS code VIPRE-01

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