Published October 1980 | Version v1
Report Restricted

Some aspects of materials development for sodium heated steam generators

Description

A development program was undertaken to support the materials selection for steam generator piping and IHX which are to be used in Liquid Metal Fast Breeder Reactors (LMFBR). Four major topics were reviewed, describing the results obtained as well as the direction of future tests. These topics are: carbon transport in sodium, effect of carbon loss/gain upon materials in the reactor Intermediate Heat Transport System (IHTS), corrosion fatigue and aqueous corrosion. The results support the initial assumptions made in specifying the use of 2-1/4Cr-1Mo as the construction material for the evaporator and superheater and Type 316 piping of the IHT system. Future direction of the experimental programs is to further verify the materials choice and to also obtain information which will be essential during the plant installation, operation and reliability of the components

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
32 p.
Report number
GEFR-SP--205

Conference

Title
Special topical meeting - materials performance in nuclear steam generators.
Dates
6 - 9 Oct 1980.
Place
St Petersburg Beach, FL, USA.

Optional Information

Secondary number(s)
CONF-801036--4.