TY - GEN
T1 - Compatibility of structural materials for fusion reactors with candidate blankets and coolants.
AU - Casteels, F.
AU - De Keyser, Ja
AU - Soenen, M.
AU - Tas, H.
AU - Dresselaers, J.
PY - 1983
Y1 - 1983
N2 - Corrosion and deposition rates and mechanisms have been determined of austenitic (AISI 316, AISI 304, AISI 316L, Nitronic 33, Nitronic 40, Carpenter 18/18 plus) and ferritic (WN 1. 4922, EM12, DT02) steels, with the light alloy Ti 6Al4V and refractory alloys (Nb, V20%Ti, TZM) exposed in the hot and cold section of a pumped loop system. The reactor loop system was operated for total exposure times up to 7400 hours with pure lithium.
AB - Corrosion and deposition rates and mechanisms have been determined of austenitic (AISI 316, AISI 304, AISI 316L, Nitronic 33, Nitronic 40, Carpenter 18/18 plus) and ferritic (WN 1. 4922, EM12, DT02) steels, with the light alloy Ti 6Al4V and refractory alloys (Nb, V20%Ti, TZM) exposed in the hot and cold section of a pumped loop system. The reactor loop system was operated for total exposure times up to 7400 hours with pure lithium.
UR - http://www.scopus.com/inward/record.url?scp=0020978440&partnerID=8YFLogxK
M3 - In-proceedings paper
AN - SCOPUS:0020978440
SN - 0444867023
T3 - Transactions of the International Conference on Structural Mechanics in Reactor Technology
BT - Transactions of the International Conference on Structural Mechanics in Reactor Technology
PB - IASMiRT - International Assn for Structural Mechanics in Reactor Technology
T2 - 1983 - SMiRT 7
Y2 - 22 August 1983 through 26 March 2019
ER -