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Technical assessment of two-phase flow aspects of nuclear reactor safety. Progress report, July 1, 1974--March 27, 1975

Technical Report ·
DOI:https://doi.org/10.2172/4237273· OSTI ID:4237273
Research Organization:
Dartmouth Coll., Hanover, N.H. (USA). Thayer School of Engineering
NSA Number:
NSA-32-002677
OSTI ID:
4237273
Report Number(s):
COO--2294-5
Country of Publication:
United States
Language:
English

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Related Subjects

*LOSS OF COOLANT-- TWO-PHASE FLOW
*PWR TYPE REACTORS-- REACTOR SAFETY
*REACTOR SAFETY
HYDRAULICS
LIQUID FLOW
N77200 --Reactors--Power Reactors
Non-breeding
Light-water Moderated
Non-boiling Water-cooled
N77900* --Reactors--Reactor Safety & Environmental Aspects