Search Results - "Shtynda, Yu E"
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1
Sodium as a coolant for fast reactors
Published in Atomic energy (New York, N.Y.) (01-08-2010)“…The results of a comparative analysis and choice of sodium as the coolant for fast reactors are presented. The facilities developed for removing impurities…”
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2
Thermohydraulic testing of a model of a sodium-water counter-current steam generator
Published in Soviet Atomic Energy (01-08-1986)Get full text
Journal Article -
3
Investigating interloop leakage for a sodium-water reverse steam generator model
Published in Soviet Atomic Energy (01-12-1987)Get full text
Journal Article -
4
Features of fault processes due to leaks of water into sodium in a counterflow steam generator
Published in Soviet Atomic Energy (01-01-1986)Get full text
Journal Article -
5
SODIUM AS A COOLANT FOR FAST REACTORS
Published in Atomic energy (New York, N.Y.) (2010)Get full text
Journal Article -
6
Some Experimental Work Performed on the BOR-60 Reactor
Published in Atomic energy (New York, N.Y.) (01-11-2001)“…The experimental work performed on a BOR-60 reactor over a period of 30 years of reactor operation is briefly reviewed. The results of investigations of the…”
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7
Some experimental work performed on the BOR-60 reactor
Published in Atomic energy (New York, N.Y.) (2002)Get full text
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