BWR feedwater nozzle and control-rod-drive return line nozzle cracking
Journal Article
·
· Nucl. Saf.; (United States)
OSTI ID:5817332
In its 1978 Annual Report to Congress, the Nuclear Regulatory Commission identified as an unresolved safety issue the appearance of cracks in feedwater nozzles at boiling-water reactors (BWRs). Later similar cracking, detected in return water lines for control-rod-drive systems at BWRs, was designated Part II of the issue. This article outlines the resolution of these cracking problems.
- OSTI ID:
- 5817332
- Journal Information:
- Nucl. Saf.; (United States), Journal Name: Nucl. Saf.; (United States) Vol. 22:6; ISSN NUSAA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Interim technical report on BWR feedwater and control rod drive return line nozzle cracking
BWR feedwater nozzle and control rod drive return line nozzle cracking: resolution of generic technical activity A-10. Technical report
BWR feedwater nozzle and control rod drive return line nozzle cracking; resolution of generic technical activity A-10. Technical report
Technical Report
·
Fri Jul 01 00:00:00 EDT 1977
·
OSTI ID:7302793
BWR feedwater nozzle and control rod drive return line nozzle cracking: resolution of generic technical activity A-10. Technical report
Technical Report
·
Fri Oct 31 23:00:00 EST 1980
·
OSTI ID:6070097
BWR feedwater nozzle and control rod drive return line nozzle cracking; resolution of generic technical activity A-10. Technical report
Technical Report
·
Mon Mar 31 23:00:00 EST 1980
·
OSTI ID:6829758
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
CONTROL ROD DRIVES
CRACKS
FEEDWATER
HYDROGEN COMPOUNDS
INSPECTION
NOZZLES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
CONTROL ROD DRIVES
CRACKS
FEEDWATER
HYDROGEN COMPOUNDS
INSPECTION
NOZZLES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS