Published 1992 | Version v1
Report

Electrochemical monitoring of ageing embrittlement of ferritic steel for high temperature reactor pressure boundary component

  • 1. Japan Atomic Energy Research Inst., Ibaraki (Japan)
  • 2. Tohoku Univ., Aramaki, Sendai (Japan)

Description

Electrochemical method was studied to apply it for the nondestructive evaluation of ageing embrittlement of 2 1/4 Cr-1Mo steel for the reactor pressure vessel of the high temperature gas-cooled reactor (HTGR) which is under construction in Japan. Isothermal ageing were conducted at temperatures from 400 deg. C to 500 deg. C for up to 50000 h for this study. Electrochemical test specimens with dimensions of 10x10x5 (mm) were taken from the undamaged portion of Charpy V-notch impact bars. In the anodic polarization curves measured in 55% Ca (NO3)2 solution, the embrittled materials show the higher secondary peak of the current density in the passive potential region. This characteristic increase in the current density corresponds to intergranular segregation of phosphorus which prevents the Formation of passive layer at grain boundaries, and the degree of the increment can be correlated with the shift of Charpy ductile to brittle transition temperature (DBTT). It is also suggested form the comparison of materials isothermally aged with and without applied stress that the enhancement of phosphorus segregation due to an applied stress is only recognized after 3000 h ageing and is diminished with increasing ageing time. (author). 13 refs, 14 figs, tab

Part of:
IAEA specialist's meeting on the integrity of pressure components of reactor systems

Additional details

Publishing Information

Imprint Title
IAEA specialist's meeting on the integrity of pressure components of reactor systems
Imprint Pagination
272 p.
Journal Page Range
p. 237-246.
Report number
INIS-mf--13935

Conference

Title
IAEA specialist's meeting on the integrity of pressure components of reactor systems.
Dates
25-29 May 1992.
Place
Paks (Hungary).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
25062323
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGING; ELECTROCHEMISTRY; EMBRITTLEMENT; FERRITIC STEELS; HTGR TYPE REACTORS; MONITORING; PRESSURE VESSELS; TEMPERATURE RANGE 0400-1000 K
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; IRON ALLOYS; IRON BASE ALLOYS; REACTORS; STEELS; TEMPERATURE RANGE

Optional Information