Published 2007 | Version v1
Miscellaneous

Effect of loading technique on stress corrosion cracking in compact tension specimens exposed in light water reactor environments

  • 1. Studsvik Nuclear AB, Nykoeping (Sweden)
  • 2. Ringhals AB, Varobacka (Sweden)
  • 3. Vattenfall Power Generation AB (Sweden)

Description

The simplest, and often the cheapest, way of achieving crack growth rate data, for instance for disposition lines, are bolt loaded specimens. Bolt loaded specimens can be exposed to simulated reactor water in laboratory loops, or to reactor water in test systems in commercially operating nuclear power plants. This type of loading is passive and one disadvantage is that the load, and consequently the stress intensity factor, is unknown once the specimen is loaded and will change due to load relaxation and crack growth. Therefore, the most common way in laboratory testing is to load specimens under either constant load or constant stress intensity factor conditions in combination with a sophisticated crack growth monitoring technique of sufficient resolution. This is an active type of loading because the load on the specimen is controlled (and measured), and it can be adjusted to the desired value. This paper compares and discusses different loading techniques and their effect on stress corrosion crack growth rates and fracture surface morphology. Compact tension specimens of Alloy 182 have been tested at constant load, constant stress intensity factor and constant displacement in BWR environments. (author)

Part of:
13th International conference on environmental degradation of materials in nuclear power systems

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-89-5
Imprint Title
13th International conference on environmental degradation of materials in nuclear power systems
Imprint Pagination
388 Megabytes
Journal Page Range
[20 p.]

Conference

Title
13. International conference on environmental degradation of materials in nuclear power systems
Dates
19-23 Aug 2007
Place
Whistler, BC (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
39116886
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
BOLTED JOINTS; CRACK PROPAGATION; CRACKING; EXPERIMENTAL DATA; LOADING; NUCLEAR POWER PLANTS; STRESS CORROSION; STRESSES
Descriptors DEC
CHEMICAL REACTIONS; CORROSION; DATA; DECOMPOSITION; INFORMATION; JOINTS; MATERIALS HANDLING; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; PYROLYSIS; THERMAL POWER PLANTS; THERMOCHEMICAL PROCESSES

Optional Information

Notes
12 refs., 3 tabs., 11 figs.