Published October 1981 | Version v1
Report Restricted

PWR steam generator tube integrity program. FY81 progress: leak rate studies on laboratory SCC steam generator tubes

Description

The Steam Generator Tube Integrity Program is part of NRC research efforts concerning primary system integrity. Past programmatic activity has involved fabrication of machined or chemicaly induced defects in Inconel 600 steam generator tubing simulating service defects. These specimens were subsequently burst or collapse tested at steam generator operating temperatures and a determination made of remaining mechanical strength. Data evaluation allowed development of mathematical formulae relating defect type and size to remaining tube integrity. Eddy current data taken on the laboratory produced defect specimens then allowed development of certainty bands about plots of defect size versus remaining tube integrity. These certain bands reflect the ability to accurately size a particular defect using single or multifrequency eddy current techniques in the laboratory

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE82004002.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
17 p.
Report number
PNL-SA--9971

Conference

Title
9. water reactor safety research information meeting.
Dates
26 - 28 Oct 1981.
Place
Washington, DC, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
13680603
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Progress Report
Descriptors DEI
DEFECTS; FAILURES; INCONEL 600; PERFORMANCE TESTING; PWR TYPE REACTORS; STEAM GENERATORS; STRESS ANALYSIS; TUBES
Descriptors DEC
ALLOYS; BOILERS; CHROMIUM ALLOYS; INCONEL ALLOYS; IRON ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ALLOYS; REACTORS; TESTING; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-811042--20.