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

Zdeněk P. Bažant; Stanley H. Fistedis

doi:10.1016/0029-5493(78)90075-4

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

Zdeněk P. Bažant^*, Stanley H. Fistedis

^*Corresponding author for this work

Civil and Environmental Engineering

Research output: Contribution to journal › Article › peer-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 language	English (US)
Pages (from-to)	317-324
Number of pages	8
Journal	Nuclear Engineering and Design
Volume	47
Issue number	2
DOIs	https://doi.org/10.1016/0029-5493(78)90075-4
State	Published - 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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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.",

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