• Anglický jazyk

Nuclear Reactor Thermal-Hydraulics

Autor: Pradip Saha

This monograph summarizes the major developments on nuclear reactor

thermal-hydraulics over the last fifty years, primarily for the

water-cooled reactors, and provides a direction for the future thermalhydraulic

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O knihe

This monograph summarizes the major developments on nuclear reactor

thermal-hydraulics over the last fifty years, primarily for the

water-cooled reactors, and provides a direction for the future thermalhydraulic

developments for water-cooled, including small modular reactors

or SMR , and Generation IV reactors. This includes discussion

on the steady-state reactor thermal hydraulics including subchannel

analysis, evolution of emergency core cooling systems (ECCS ) from active

to fully passive systems to remove the decay heat, and development

and consolidation of the best-estimate safety analysis methodology.

With substantial increase in computing power, the computational fluid

dynamics (CFD ) tools for single-phase and multi-phase flows are being

used more these days to address some of the important reactor thermalhydraulics

phenomena which could not be analyzed earlier using the

traditional one-dimensional or coarse three-dimensional analysis tools.

Development of multi-physics methodology encompassing neutronics,

thermal-hydraulics, thermal-mechanical and coolant chemistry has also

started.

ASME_

  • Vydavateľstvo: ASME Press
  • Rok vydania: 2017
  • Formát: Hardback
  • Rozmer: 235 x 157 mm
  • Jazyk: Anglický jazyk
  • ISBN: 9780791861288

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