Published 1993 | Version v1
Book

Post-irradiation annealing effects on hardness and IASCC susceptibility in stainless steels

  • 1. Nuclear Engineering Laboratory, Yokohama (Japan)
  • 2. Tohoku Univ., Oarai (Japan)

Description

The effects of post-irradiation annealing on hardness and grain boundary corrosion related to stress corrosion were investigated on type 304 and 304L stainless steels irradiated to 5.3 x 1024 n/m2 (E>1 MeV). Hardness tests, 10% oxalic acid tests and double loop electrochemical potentiokinetic reactivation (EPR) tests were conducted after annealing at 400 to 1000 degrees C for one hour. Radiation anneal hardening was observed at 500 degrees C and was more pronounced on alloys containing a higher amount of C and Si. The hardness recovered by annealing at 600 degrees C and above. In the oxalic acid tests, the irradiated type 304 stainless steel was sensitized as well as the unirradiated specimen, and grain boundary attack in the former was slightly pronounced than in the latter. In the EPR test, the surface morphology and the annealing temperature dependence of the reactivation ratio in the irradiated specimens were different from those in the unirradiated specimens. These differences indicated that changes in Cr carbide an Cr depletion near the grain boundary during annealing would be influenced by a pre-existing irradiation induced microstructure and grain boundary segregation. Annealing at 1000 degrees C resulted in a full recovery of hardness, grain boundary corrosion and IGSCC susceptibility determined by a slow rate (SSR) test in high temperature water

Additional details

Publishing Information

Publisher
Minerals, Metals ampersand Materials Society.
Imprint Place
Warrendale, PA (United States)
Imprint Title
Proceedings of the sixth international symposium on environmental degradation of materials in nuclear power systems - water reactors
Imprint Pagination
963 p.
Journal Page Range
p. 555-562.

Conference

Title
water reactors.
Acronym
6. international symposium on environmental degradation of materials in nuclear power systems
Dates
1-5 Aug 1993.
Place
San Diego, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25066144
Subject category
S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANNEALING; GRAIN BOUNDARIES; HARDNESS; IRON BASE ALLOYS; IRRADIATION; STAINLESS STEELS; STRESS CORROSION
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CORROSION; CRYSTAL STRUCTURE; HEAT TREATMENTS; HIGH ALLOY STEELS; IRON ALLOYS; MECHANICAL PROPERTIES; MICROSTRUCTURE; STEELS

Optional Information

Secondary number(s)
CONF-930825--.