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Stress Corrosion Studies for the Clinch River Breeder Reactor Steam Generator

Technical Report ·
DOI:https://doi.org/10.2172/7235540· OSTI ID:7235540
 [1]
  1. General Electric Co., Sunnyvale, CA (United States). Fast Breeder Reactor Dept.
The steam generator of the Clinch River Breeder Reactor is to be constructed with 2-1/4 Cr--1 Mo steel. The alternate material of construction is Incoloy-800. The susceptibility of 2-1/4 Cr--1 Mo and Incoloy-800 to caustic cracking in badly faulted high temperature aqueous and superheated steam environments was determined. Except for a few experiments at 450°F that were required to understand the mechanism of caustic cracking, all of the experiments were conducted in aqueous solutions at 316°C (600°F) and in superheated steam at 482°C (900°F). These temperatures are the approximate operating temperatures of the evaporator and superheater sections of the Clinch River Breeder Reactor. Results are presented and discussed.
Research Organization:
General Electric Co., Sunnyvale, CA (United States). Fast Breeder Reactor Dept.
Sponsoring Organization:
US Energy Research and Development Administration (ERDA)
DOE Contract Number:
E(04-3)-0893-TAS-18
OSTI ID:
7235540
Report Number(s):
GEAP--14118
Country of Publication:
United States
Language:
English