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Title: REACTOR PRIMARY COOLANT SYSTEM RUPTURE STUDY. Quarterly Report No. 23, October--December 1970.

Technical Report ·
DOI:https://doi.org/10.2172/4005222· OSTI ID:4005222

Research Organization:
General Electric Co., Sunnyvale, Calif. Breeder Reactor Development Operation
DOE Contract Number:
AT(04-3)-189
NSA Number:
NSA-25-028680
OSTI ID:
4005222
Report Number(s):
GEAP-10207-23
Resource Relation:
Other Information: UNCL. Orig. Receipt Date: 31-DEC-71
Country of Publication:
United States
Language:
English

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Related Subjects

N38140* -Power Reactor Development-Cooling Systems
N30130 -Metals
Ceramics
& Other Materials-Metals & Alloys-Properties Evaluations
BOILING WATER REACTORS
CARBON STEELS
COOLANT LOOPS
CRACKS
FAILURES
FATIGUE
PIPES
STAINLESS STEELS
STRESSES
WATER COOLED REACTORS
REACTORS
BOILING/cooling systems for
testing of low- cycle fatigue life of carbon and stainless steel piping in
(E)
STEEL/crack initiation and growth in carbon
effects of low-cycle fatigue on
(E)
REACTORS
WATER-COOLED/cooling systems for
failure mechanisms in piping of
(E/T)
PIPES/ failure in reactor cooling systems
probability analysis of
PIPES/crack initiation and growth in reactor cooling system
effects of low-cycle fatigue on
(E)
STAINLESS STEEL/crack initiation and growth in Type 304
effects of low- cycle fatigue on
(E)