Published 1983 | Version v1
Report Open

Mechanism of TMI-1 steam-generator failures

Creators

Description

The low-temperature stress-corrosion cracking (SCC) of sensitized Inconel 600 was studied using various borated solutions of sulfur compounds. Sodium thiosulfate and sodium tetrathionate were equally aggressive provided that the alloy was sufficiently severely sensitized. Tetrathionate was more effective on marginally sensitized material. The threshold concentration of thiosulfate was below 10-6 M. LiOH additions inhibited SCC. Oxygen is necessary for SCC in these solutions. The relevance of the laboratory tests to the steam generator failures is discussed

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as DE83015770.

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Additional details

Publishing Information

Imprint Pagination
22 p.
Report number
BNL-NUREG--33385

Conference

Title
Conference on environmental degradation of materials in nuclear power systems-water reactors.
Dates
22-24 Aug 1983.
Place
Myrtle Beach, SC (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15010189
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALLOY-NI76CR15FE8; FAILURES; REACTOR MATERIALS; STEAM GENERATORS; STRESS CORROSION; THREE MILE ISLAND-1 REACTOR; TUBES; WATER CHEMISTRY
Descriptors DEC
ALLOYS; ALUMINIUM ADDITIONS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; TITANIUM ADDITIONS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER TREATMENT

Optional Information

Secondary number(s)
CONF-830845--1.