Sodium boiling experiments in an inductively heated test loop. Natrium-siedestossexprimente in einem groesseren kreislauf unter verwendung induktiv beheizter teststrecken

Technical Report · Tue Apr 15 00:00:00 EST 1969

OSTI ID:4184439

Peppler, W.

Paper IX.

• Research Organization: Kernforschungszentrum, Karlsruhe (Germany). Institut fur Reaktorentwicklung
• Sponsoring Organization: Kernforschungszentrum, Karlsruhe (Germany)
• NSA Number: NSA-24-018633
• OSTI ID: 4184439
• Report Number(s): KFK-964; EUR-4171-d; CONF-690419-
• Resource Relation: Conference: 1969 Reactor Conference of the German Atomic Forum, 15-18 April 1969, Frankfurt (Germany). Beitrage zur Reaktortagung 1969 des Deutschen Atomforums; Related Information: In: Development of fast breeder reactors. 1969 Reactor Conference of the German Atomic Forum, 15-18 April 1969, Frankfurt am Main, Germany. Beitrage zur Reaktortagung 1969 des Deutschen Atomforums, 143 p.
• Country of Publication: Germany
• Language: German

Related Subjects

N38140* -Power Reactor Development-Cooling Systems
BOILING
MEASUREMENT
METAL COOLED REACTORS
SAFETY
SHOCK WAVES
SODIUM
TESTING
SODIUM/boiling shock characteristics of liquid
measurement of
(E)
REACTORS
LIQUID METAL-COOLED/coolant of
measurement of boiling shock characteristics of liquid sodium
(E)
BOILING/characteristics of liquid sodium
measurement of shock actuating
(E)