Published 1978 | Version v1
Book

Waterside corrosion of stabilised 2 1/4%Cr-1%Mo ferritic steel under high heat flux conditions

  • 1. UKAEA, Harwell. Atomic Energy Research Establishment

Description

The waterside corrosion of stabilised 2 1/4%Cr 1%Mo ferritic steel tubes has been studied under conditions which simulate the inlet region of a Prototype Fast Reactor (PFR) evaporator. The amount of corrosion occurring in times from 1000 to 3400 hours was found to be unaffected by: thermal and pressure changes which simulate extreme conditions in the plant; 1 ppm NaCl or 7 ppm NaOH in the loop water; steam quality; heat flux; tube surface condition; the presence of large defects. Large defects in the heat flux zone were able to concentrate soluble species present in the loop water. The presence of a high heat flux (660 kW/m2) resulted in an increased deposition of non-porous magnetite onto the tube surface. (author)

Additional details

Publishing Information

Publisher
British Nuclear Energy Society.
Imprint Place
London
ISBN
0 7277 0049 0
Imprint Title
Ferritic steels for fast reactor steam generators. Proceedings of an international conference held by the British Nuclear Energy Society at the Institution of Civil Engineers, London 30 May - 2 June 1977
Journal Page Range
p. 353-359.

Conference

Title
International conference on ferritic steels for fast reactor steam generators.
Dates
30 May - 2 Jun 1977.
Place
London, UK.

Optional Information

Notes
Imprint:In 2 volumes.