Published October 2005 | Version v1
Journal article Metadata-only

Crack growth rate in initiation stage on primary water stress corrosion cracking of alloy 600 weld metals

Creators

  • 1. Inst. of Nuclear Safety System, Inc., Inst. of Nuclear Technology, Mihama, Fukui (Japan)

Description

Crack growth rates in initiation stage on primary water stress corrosion cracking (PWSCC) were studied at temperature 360degC using constant load test to clarify the PWSCC behavior of alloy 600 weld metals and Ti and/or Nb containing MA600. As the results, it is revealed that crack growth rate of alloy 600 weld metals are 3 to 5 times faster than that of MA600, and those of Ti and/or Nb containing material is nearly MA600 at the same normalized stress using each 0.2% proof stress, though they show slower rate at the same stress. (author)

Additional details

Publishing Information

Journal Title
INSS Journal
Journal Volume
12
Journal Page Range
p. 170-176
ISSN
1340-4482

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
37067639
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ADDITIVES; CRACK PROPAGATION; CRACKING; INCONEL 600; NIOBIUM; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STATIC LOADS; STRESS CORROSION; TITANIUM; WELDED JOINTS
Descriptors DEC
ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; DECOMPOSITION; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; JOINTS; MATERIALS; METALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; POWER REACTORS; PYROLYSIS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REFRACTORY METALS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
9 refs., 19 fig., 4 tabs.