Behavior of short flaws during thermal shock: thermal-shock experiment TSE-7
Thermal-shock experiment TSE-7 was designed for the investigation of the behavior of a short, axially oriented flaw on the inner surface of an unclad, thick-walled, steel cylinder that was to be subjected to a severe thermal shock. Calculations indicated that the flaw would extend on the surface, possibly the full length of the cylinder in a single event, and subsequent events would extend the depth of the flaw to approx. fifty percent of the wall thickness. If the flaw did in fact extend on the surface a substantial amount, then a similar follow on experiment with a clad cylinder would reveal the effect of the cladding. Thus, the purpose of TSE-7 was twofold: (1) study the behavior of initially short surface flaws under simulated PWR thermal-shock loading conditions, but without cladding, and (2) TSF-7 was to constitute a base case for a series of cladding-effects experiments.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5323863
- Report Number(s):
- CONF-8310143-13; ON: DE84001941
- Resource Relation:
- Conference: 11. NRC water reactor safety research information meeting, Gaithersburg, MD, USA, 14 Oct 1983; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRESSURE VESSELS
THERMAL SHOCK
PWR TYPE REACTORS
TRANSIENTS
DEFECTS
PERFORMANCE TESTING
REACTOR SAFETY
STRESS ANALYSIS
CONTAINERS
REACTORS
SAFETY
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled