Susceptibility to Severe PWSCC (primary water stress corrosion cracking) of LTMA (low temperature mill anneal) Alloy 600
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. MACTEC (Materials Core Technology Center), Daejeon (Korea, Republic of)
Description
It has been proposed that a primary water stress corrosion cracking (PWSCC) in pressurized water reactor (PWR) is governed by a lattice contraction due to a short range ordering reaction in Alloy 600. This leads researcher to think that the kinetics of lattice contraction may control a susceptibility of PWSCC in Alloy 600. A lattice variation with ordering treatment at 400 °C was systematically investigated using high resolution neutron diffraction(HRPD) in high temperature mill anneal (HTMA), low temperature mill anneal (LTMA), and sensitized (SEN) Alloy 600. The results showed that ordering treatment caused an isotropic lattice contraction due to short range ordering (SRO) reaction. The lattice contractions of (111) plane are saturated to be 0.04% in 4 to 1500 hours at 400 °C according to prior treatment condition. The lattice contraction in the magnitude of 0.03% of (111) plane in LTMA Alloy 600 is faster by 8 times and 66 times than that of SEN and HTMA, respectively. This fact may explain why the LTMA is most susceptible to PWSCC through of kinetics of lattice contraction in Alloy 600. Thus, it is possible to conclude that the susceptibility of Alloy 600 to PWSCC is governed by the kinetics of (111) lattice contraction.
Additional details
Publishing Information
- Journal Title
- Journal of the Korean Institute of Metals and Materials
- Journal Volume
- 58
- Journal Issue
- 12
- Series
- 18 refs, 7 figs, 1 tab
- Journal Page Range
- p. 815-821
- ISSN
- 1738-8228
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 52085171
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ANNEALING; CONTRACTION; CRACKING; CRYSTAL LATTICES; INCONEL 600; NEUTRON DIFFRACTION; PWR TYPE REACTORS; STRESS CORROSION
- Descriptors DEC
- ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; COHERENT SCATTERING; CORROSION; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DECOMPOSITION; DIFFRACTION; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAT TREATMENTS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; POWER REACTORS; PYROLYSIS; REACTORS; SCATTERING; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS