Dried hot concrete vessel for nuclear reactors: Proposal of a new design concept

Zdeněk P. Bažant*, Stanley H. Fistedis

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

1 Scopus citations

Abstract

The paper discusses special features of the concept of a dried hot prestressed concrete reactor vessel for pool-type liquid-metal cooled fast breeder reactors. In particular, the potentially advantageous feature of removing evaporable water from concrete when it is being kept hot is discussed along with its technological implications.

Original languageEnglish (US)
Pages (from-to)317-324
Number of pages8
JournalNuclear Engineering and Design
Volume47
Issue number2
DOIs
StatePublished - May 2 1978

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

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