Actions for Hazards Analysis. Effects of Steam Generator Tube Rupture

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Hazards Analysis. Effects of Steam Generator Tube Rupture

Author
Gage, A. H.
Published
United States : [publisher not identified], 1960.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1960.
Physical Description
microfiche : negative ; 8 x 13 cm

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Summary
A review of the basis for sizing the EGCR coolant system relief valves is presented. The possible effects of steam-graphite reaction in event of a boiler tube failure are also considered along with hazards of steam generator water side depressurization.
Report Numbers
ACNP-61517; EGCR-STUDY-IV-316(
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: AT(10-1)-925
NSA number: NSA-17-021302
OSTI Identifier 4715230
Research organization: Allis-Chalmers Mfg. Co. Atomic Energy Div., Washington, D.C.
Funding Information
Sponsored by US Atomic Energy Commission (AEC).
View MARC record | catkey: 38681619