Shippingport aging studies: Results and plans
The objective of this program is to develop an understanding of the metallurgical phenomena that may occur in nuclear reactor structural materials as a consequence of extended service at operating temperatures within and outside of the radiation environment and to assess the impact of these phenomena on structural integrity. Although many aging phenomena such as the embrittlement of cast stainless steel, low-temperature sensitization of austenitic stainless steels, and radiation embrittlement of pressure vessel steels have been studied in the laboratory, most of the studies have been based on simulation of actual reactor conditions. The Shippingport reactor offers a unique opportunity to validate and benchmark the laboratory studies, and thereby, provide a sound basis for evaluating the integrity of structural components near the end of the projected life of the plant. Additional work will be undertaken to identify the possibility of new, previously unknown mechanisms of component degradation. 6 refs., 10 figs., 6 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6829952
- Report Number(s):
- CONF-8810155-23; ON: DE89003632; TRN: 89-002052
- Resource Relation:
- Conference: 16. water reactor safety information meeting, Gaithersburg, MD, USA, 24 Oct 1988; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Mechanical properties of thermally aged cast stainless steels from Shippingport reactor components
Mechanical properties of thermally aged cast stainless steels from shippingport reactor components.
Related Subjects
36 MATERIALS SCIENCE
SHIPPINGPORT REACTOR
AGING
MECHANICAL PROPERTIES
METALLURGICAL EFFECTS
PLANNING
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
STAINLESS STEELS
ALLOYS
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
STEELS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360103 - Metals & Alloys- Mechanical Properties
360106 - Metals & Alloys- Radiation Effects