Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.015 seconds
Mayfield, M.E.; Rodabaugh, E.C.; Eiber, R.J.
Battelle Columbus Labs., OH (USA)1978
Battelle Columbus Labs., OH (USA)1978
AbstractAbstract
[en] The ''cold leg'' in a PWR is defined as that portion of the primary coolant loop that lays between the coolant pump and the reactor vessel. One of the conditions which may lead to failure in a cold leg consists of repeated cycles of stress. These repeated stress cycles may cause the growth of any small defect in the weld or base material and, if the stress cycles are high enough and frequent enough, the defect may grow until it penetrates the wall, resulting in a leak, or under some postulated conditions, a large break might occur. The objective of this report is to present an evaluation of available fatigue test data on piping products to determine the margin of safety of the present ASME code method of evaluation; to determine the leak-rupture trends of components tested with significant internal pressures; and to determine the implications of the tests with respect to the cold leg piping systems in PWR's
Original Title
PWR
Primary Subject
Secondary Subject
Source
Jul 1978; 102 p; Available from NTIS., PC A06/MF A01
Record Type
Report
Report Number
Country of publication
ALLOYS, CARBON ADDITIONS, CARBON STEELS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, COOLING SYSTEMS, CORROSION RESISTANT ALLOYS, HEAT RESISTING ALLOYS, IRON ALLOYS, IRON BASE ALLOYS, JOINTS, MECHANICAL PROPERTIES, NICKEL ALLOYS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, STAINLESS STEELS, STEELS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue