Published 1977 | Version v1
Book

Heavy-section steel technology program intermediate-scale pressure vessel tests

  • 1. Oak Ridge National Lab., TN (USA)

Description

Eight intentionally flawed thick-walled pressure vessels of ASTM A508 class 2 forging steel or A533, grade B, class 1 steel plate have been pressurized to fracture or leak. Tests of these vessels (990 mm OD, 152 mm wall thickness) permitted the study of fracture behavior of structures under stress states not attainable with conventional testing machines. The test section thickness was chosen in order to provide a test configuration that was essentially full-scale relative to BWR and PWR pressure vessels. Experimental results were used to evaluate and improve methods of fracture analysis that could be used in predicting failure conditions of reactor type vessels. (Auth.)

Additional details

Publishing Information

Publisher
North-Holland.
Imprint Place
Amsterdam, Netherlands
ISBN
0 444 85062 7
Imprint Title
Structural mechanics in reactor technology
Journal Page Range
v. G p. G1/1 1-11.

Conference

Title
4. international conference on structural mechanics in reactor technology.
Dates
15 - 19 Aug 1977.
Place
San Francisco, USA.

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
10433548
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEFECTS; FRACTURE PROPERTIES; FRACTURES; LEAKS; PERFORMANCE TESTING; PRESSURE VESSELS; STEEL-ASTM-A508; STEEL-ASTM-A533-B; STRESSES
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CARBON STEELS; CONTAINERS; FAILURES; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; STEELS; TESTING; TRANSITION ELEMENT ALLOYS