LABORATORY SIMULATIONS OF CLADDING-STEAM REACTIONS FOLLOWING LOSS-OF- COOLANT ACCIDENTS IN WATER-COOLED POWER REACTORS.

Technical Report · Thu Jan 01 00:00:00 EST 1970

DOI:https://doi.org/10.2172/4132278· OSTI ID:4132278

Hesson, J C; Ivins, R O; Wilson, R E; Nishio, K; Barnes, C Jr

• Research Organization: Argonne National Lab., Ill.
• DOE Contract Number: W-31-109-ENG-38
• NSA Number: NSA-24-036043
• OSTI ID: 4132278
• Report Number(s): ANL-7609
• Resource Relation: Other Information: UNCL. Orig. Receipt Date: 31-DEC-70
• Country of Publication: United States
• Language: English

Related Subjects

N38180* -Power Reactor Development-Safety & Siting
N30110 -Metals
Ceramics
& Other Materials-Metals & Alloys-Corrosion & Erosion & Surface Phenomena
ACCIDENTS
BRITTLENESS
CHEMICAL REACTIONS
FUEL CANS
HIGH TEMPERATURE
HYDROGEN
LOSSES
OXIDATION
POWER REACTORS
STAINLESS STEEL-304
STEAM
WATER COOLANT
WATER COOLED REACTORS
ZIRCALOY
STAINLESS STEEL/oxidation of Type 304
by steam following coolant loss accidents in water cooled reactors
(E)
ZIRCALOY-2/ oxidation by steam following coolant loss accidents in water cooled reactors
(E)
STEAM/reactions with Type 304 stainless steel and Zircaloy-2 following coolant loss accidents in water cooled reactors
(E)
REACTORS
WATER-COOLED/coolant loss accidents in
steam reactions with fuel element cladding following
(E)
REACTOR FUEL ELEMENTS/cladding for water cooled
high temperature steam reactions with
(E)