Published April 1997 | Version v1
Miscellaneous

Thermal recovery characteristics of Kori-unit 1 linde 80 weld

  • 1. Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)
  • 2. Korea Advanced Inst. of Science and Technology, Taejon (Korea, Republic of)

Description

The recovery activation energy, the order of reaction and the characteristic recovery rate constant were determined by isochronal (573K -823K) and isothermal (723K - 775K) annealing experiments on specimens made from a broken half of a Kori-Unit 1 surveillance weld specimen (fluence: 1.21 x 1023 n/m2, E (1MeV, Cu: 0.29 wt%) to investigate the recovery characteristics of a high copper weld of neutron-irradiated reactor pressure vessel (RPV). Vickers microhardness tests were conducted to trace the recovery behavior after heat treatments. The results were analyzed in terms of recovery stages, behavior of responsible defects and recovery kinetics. It was shown that recovery occurred through two annealing stages (stage I: 673K - 753K, stage II: 753K - 823K) with recovery activation energies of 2.68 eV and 2.83 eV for stage I and II, respectively. The isothermal hardness recovery at 723 K and 775 K coincided with the ratio of the characteristic rate constant for each recovery stage. The order of reaction was 2 for both recovery stages. The recovery activation energies of present specimens are approximately equal to that of copper diffusion in α-iron in the presence of vacancies, suggesting that recovery may occur through the diffusion of copper atoms. The present results strongly support the copper precipitate coarsening model. (author)

Availability note (English)

Available from KAERI.
Part of:
Proceedings of the 12th KAIF/KNS annual conference

Additional details

Publishing Information

Publisher
Korea Atomic Industrial Forum Inc. and Korean Nuclear Society.
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
Proceedings of the 12th KAIF/KNS annual conference
Imprint Pagination
808 p.
Journal Page Range
p. 651-666.

Conference

Title
12. KAIF/KNS annual conference.
Dates
3-4 Apr 1997.
Place
Seoul (Korea, Republic of).

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
29009499
Subject category
S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AFTER-HEAT; HEAT TREATMENTS; KORI-1 REACTOR; MICROHARDNESS; PRESSURE VESSELS; REACTOR VESSELS; THERMODYNAMIC PROPERTIES; THERMODYNAMICS
Descriptors DEC
CONTAINERS; ENRICHED URANIUM REACTORS; HARDNESS; MECHANICAL PROPERTIES; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information