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BS 4975:1973

Specification for prestressed concrete pressure vessels for nuclear reactors

Standard Details

Deals with the design, construction, inspection and testing of prestressed concrete pressure vessels for nuclear reactors. Such pressure vessels serve the dual purpose of shielding and containing gas cooled nuclear reactors and are a form of civil engineering structure requiring particularly high integrity, and ensured leak tightness.

General Information

Status : WITHDRAWN
Standard Type: Main
Document No: BS 4975:1973
Document Year: 1973
  • Section Volume:
  • GBM16 Energy & Heat Engineering (GMB16)

Life Cycle

Confirmed

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WITHDRAWN
BS 4975:1973
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