PWR containment structures license renewal industry report: Revision 1. Final report
Technical Report
·
OSTI ID:72961
- Bechtel Power Corp., Gaithersburg, MD (United States)
Reinforced concrete, prestressed concrete, and freestanding steel PWR containment structures and components have been evaluated relative to the effects of age-related degradation mechanisms; the capability of current design limits, inservice examination, testing, repair, refurbishment, and other programs to manage these effects; and the assurance that these structures and components can continue to perform their intended safety functions in the license renewal term. This industry report (IR), one of a series of ten, provides a generic technical basis for evaluation of PWR containment structures and components for license renewal.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (United States); Bechtel Power Corp., Gaithersburg, MD (United States)
- Sponsoring Organization:
- Electric Power Research Inst., Palo Alto, CA (United States)
- OSTI ID:
- 72961
- Report Number(s):
- EPRI-TR--103835
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
AGING
CONTAINMENT BUILDINGS
CONTAINMENT SYSTEMS
CORROSION
IN-SERVICE INSPECTION
NUCLEAR POWER PLANTS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
REACTOR LICENSING
REACTOR MAINTENANCE
RELIABILITY
SERVICE LIFE
STANDARDS
22 GENERAL STUDIES OF NUCLEAR REACTORS
AGING
CONTAINMENT BUILDINGS
CONTAINMENT SYSTEMS
CORROSION
IN-SERVICE INSPECTION
NUCLEAR POWER PLANTS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
REACTOR LICENSING
REACTOR MAINTENANCE
RELIABILITY
SERVICE LIFE
STANDARDS