TY - GEN
T1 - Recovery of the transition temperature of irradiated WWER-440 vessel metal by annealing
AU - Amayev, Amir D.
AU - Kryukov, Alexander M.
AU - Sokolov, Mikhail A.
PY - 1993
Y1 - 1993
N2 - The main results obtained from studying recovery of irradiation embrittlement of reactor vessel steels are presented. Investigations were carried out using WWER-440 vessel materials (base metal, weld metal). The irradiation temperature was 270°C, which corresponded to the operation temperature of the vessel wall. The effect of the annealing temperature and annealing time, neutron fluence, and phosphorus and copper impurity contents on recovery of the ductile-to-brittle transition temperature was studied. Recovery of the transition temperature depends mainly on the annealing temperature. At a phosphorus content exceeding 0.02%, recovery of properties in annealing is complicated. The effect of copper at contents lower than 0.2% has not been observed. At an annealing temperature of 420°C, residual postannealing embrittlement does not depend on neutron fluence. The results obtained in irradiation-annealing-reirradiations are also presented. After annealing, the tendency of the steel to irradiation embrittlement is not increased over that in its initial state.
AB - The main results obtained from studying recovery of irradiation embrittlement of reactor vessel steels are presented. Investigations were carried out using WWER-440 vessel materials (base metal, weld metal). The irradiation temperature was 270°C, which corresponded to the operation temperature of the vessel wall. The effect of the annealing temperature and annealing time, neutron fluence, and phosphorus and copper impurity contents on recovery of the ductile-to-brittle transition temperature was studied. Recovery of the transition temperature depends mainly on the annealing temperature. At a phosphorus content exceeding 0.02%, recovery of properties in annealing is complicated. The effect of copper at contents lower than 0.2% has not been observed. At an annealing temperature of 420°C, residual postannealing embrittlement does not depend on neutron fluence. The results obtained in irradiation-annealing-reirradiations are also presented. After annealing, the tendency of the steel to irradiation embrittlement is not increased over that in its initial state.
UR - http://www.scopus.com/inward/record.url?scp=0027205754&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:0027205754
SN - 0803114788
T3 - ASTM Special Technical Publication
SP - 369
EP - 379
BT - ASTM Special Technical Publication
PB - Publ by ASTM
T2 - IAEA Specialists' Meeting on Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels
Y2 - 26 September 1990 through 29 September 1990
ER -