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
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.