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

Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors

IAEA-TECDOC-1654

English IAEA-TECDOC-1654 | 978-92-0-108910-6

240 pages | € 18.00 | Date published: 2010

Download PDF (7.71 MB)

Description

This publication is the proceedings of a technical meeting on enhancement of efficiency of nuclear power through increased fuel utilization and better performance. It provides an overview of the current status in the development of fuel pellet material and of improvements in fuel rod designs for light and heavy water cooled power reactors. The meeting participants focused their discussions on modern technological and design tools enabling reliable fuel performance in current and planned operational environments, analysed high burn-up fuel structure and properties as well as specific features of advanced fuels. In addition, there was a round-table discussion that addressed the regulatory aspects of fuel quality assurance.

More Information on reusing IAEA copyright material.

Related publications

Stay in touch

Newsletter