ROCKWELL INTERNATIONAL CANOGA PARK CA ATOMICS INTERNATIONAL DIV
Click on the titles below to find US government-authored or -collected reports written by ROCKWELL INTERNATIONAL CANOGA PARK CA ATOMICS INTERNATIONAL DIV
The mechanical properties of candidate cladding materials for fast breeder reactor fuel elements are being investigated as part of the Atomic Energy Commission Liquid Metal Cooled Past Breeder Reactor Program. This report deals with the stress-rupture characteristics of austenitic stainless steels in a liquid sodium environment, in both cold-worked and annealed conditions.
The results of stress-rupture tests of internally heated and pressurized thin-walled tubes of Type 304 stainless steel are presented. The tubes were immersed in high-purity sodium at 1200 deg F and at a flow rate of 20 ft/sec. A heat flux of 10(exp 6) Btu/sq ft-hr passed through the wall. The heat flux was applied in three modes: steady; 6-min on, 6-min off; and 1-min on, 1- ...