THERMOCYCLIC RECOVERY AND DAMAGE ACCUMULATION OF IRRADIATED AUSTENITIC STRUCTURAL-MATERIALS

Citation
La. Belyaeva et Vv. Rybin, THERMOCYCLIC RECOVERY AND DAMAGE ACCUMULATION OF IRRADIATED AUSTENITIC STRUCTURAL-MATERIALS, Journal of nuclear materials, 237, 1996, pp. 224-228
Citations number
12
Categorie Soggetti
Nuclear Sciences & Tecnology","Mining & Mineral Processing","Material Science
ISSN journal
00223115
Volume
237
Year of publication
1996
Part
A
Pages
224 - 228
Database
ISI
SICI code
0022-3115(1996)237:<224:TRADAO>2.0.ZU;2-W
Abstract
Thermocyclic behaviour of austenitic materials: 16%Cr-11%Ni, 16%Cr-15% Ni, 20%Cr-45%Ni has been investigated after being irradiated in WWR an d BOR-60 reactors at a temperature of about 300 degrees C up to fluenc es of approximately 10(25) and 10(26) n/m(2). Strength and strain char acteristics of irradiated materials are recovered during thermocycling (50-300 degrees C) and reached initial unirradiated values. Simultane ously to the recovery processes an intensive accumulation of thermocyc lic damage takes place with early material fracture. Thermal fatigue f ailure has shown an intergranular mode. It is assumed that two opposit e processes take place during thermocycling: recovery in grain volume and the accumulation of damage along grain boundaries, which do not co mpensate each other.