亚洲av无码久久精品狠狠爱浪潮_高清精品一区二区三区_中文乱码字慕人妻熟女人妻_国产熟妇疯狂4p交在线播放_国产成人无码av

  • English
  • ???????
  • 中文
  • Fran?ais
  • Русский
  • Espa?ol

You are here

Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs)

IAEA-TECDOC-1746

English IAEA-TECDOC-1746 | 978-92-0-107614-4

508 pages | € 18.00 | Date published: 2014

Download PDF (10.81 MB)

Description

In order to develop the supercritical water cooled reactor (SCWR) concept, thermohydraulics of supercritical pressure water is one of the most important areas to be clarified. This publication summarizes the outcome of an IAEA coordinated research project (CRP) on this topic. It provides researchers and engineers with a comprehensive and reliable thermohydraulics database and the current status of prediction methods for SCWR concept development. The publication includes descriptions of SCWR concepts, heat transfer and pressure loss characteristics of supercritical pressure fluids, development of new heat transfer prediction methods, critical flow during depressurization from supercritical conditions, and flow stability and natural circulation in supercritical pressure systems. It also covers the results of two code testing benchmark exercises for steady state heat transfer and flow stability in a heated channel.

More Information on reusing IAEA copyright material.

Related publications

Stay in touch

Newsletter