Published 2000 | Version v1
Miscellaneous Metadata-only

Irradiation embrittlement and recovery in Kori-1 Linde 80 weld

Creators

  • 1. Korea Atomic Energy Research Inst., Yusung (Korea, Republic of)

Description

The results of Kori-1 reactor surveillance concerning the state of a pressure vessel weld during operation as well as after thermal recovery of weld metal are under discussion. The properties of unirradiated specimens are compared with tensile and impact Charpy test results for reactor irradiated specimens of Linde 80 (0.29 % Cu) weld metal, HAZ and base metal. It is revealed that noticeable embrittlement of weld metal mainly proceeds at the first stage of reactor operation, if radiation dose is as great as 5·1018 n/cm2 the growth of embrittlement becomes inconsiderable. It is shown that the annealing within 400-480 deg C results in practically complete recovery of base metal properties whereas the Linde 80 weld metal cannot be fully recovered even in holding at 550 deg C for 4 h

Abstract (Russian)

Обсуждаются результаты наблюдения за состоянием сварного шва корпуса реактора Кори-1 в процессе эксплуатации, а также результаты экспериментов по термическому восстановлению металла шва. Свойства необлученных образцов сравниваются с результатами испытаний на растяжение и ударных испытаний по Шарпи для облученных в реакторе образцов металла шва Linde 80 (0.29 % Cu), зоны термического влияния и основного металла. Установлено, что заметное охрупчивание сварного шва происходит уже на ранней стадии работы реактора, и после достижения дозы около 5·1018 н/см2 его увеличение незначительно. Показано, что применение восстановительного отжига при 400-480 град С приводит к практически полному восстановлению свойств основного металла, в то время как металл шва Linde 80 восстанавливается не полностью даже при выдержке 550 град С в течение 4 ч
Part of:
Proceedings of the sixth international conference on material issues in design, manufacturing and operation of nuclear power plants equipment. Volume 1

Additional details

Publishing Information

Imprint Place
St. Petersburg (Russian Federation)
Imprint Title
Proceedings of the sixth international conference on material issues in design, manufacturing and operation of nuclear power plants equipment. Volume 1
Imprint Pagination
290 p.
Journal Page Range
p. 113-124
Report number
INIS-RU--452

Conference

Title
6. international conference on material issues in design, manufacturing and operation of nuclear power plants equipment
Dates
19-23 Jun 2000
Place
St. Petersburg (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
32054520
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ANNEALING; FRACTURE PROPERTIES; HARDNESS; HEAT AFFECTED ZONE; KORI-1 REACTOR; LOW ALLOY STEELS; PRESSURE VESSELS; RADIATION HARDENING; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0400-1000 K; ULTIMATE STRENGTH; WELDED JOINTS; YIELD STRENGTH
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; HARDENING; HEAT TREATMENTS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MECHANICAL PROPERTIES; PHYSICAL RADIATION EFFECTS; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTORS; STEELS; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZONES

Optional Information

Notes
12 refs., 9 figs., 3 tabs.