SIMULATED BOILING WATER REACTOR AND SUPERHEAT REACTOR CORROSION FACILITY

Journal Article · Sun Sep 01 04:00:00 EDT 1963 · Nuclear Science and Engineering (U.S.)

OSTI ID:4630417

Fitzsimmons, M D; Pearl, W L; Siegler, M

A versatile boiling water and superheated steam facility was developed for out-of-pile corrosion testing of materials that are being used and considered for application in boiling water reactor (BWR) and superheat reactor (SHR) systems. The following capabilities were achieved: simulation of the various environments (other than irradiation) that would contact materials in a Dresden type BWR and an SHR utilizing steam generated therefrom; dynamic fuelcladding material tests operated with a heat flux of 250,000 sentative BWR heat transfer conditions; dynamic fuelcladding-material tests operated with a heat flux of 170,000 SHR heat-transfer conditions; control of oxygen and hydrogen content in the steam and water to simulate the gas conditions from radiolytic water decomposition found in a BWR; and (5) attainment of metal temperatures of 1300 deg F while superheating steam to 1050 deg F. (auth)

• Research Organization: General Electric Co., San Jose, Calif.
• NSA Number: NSA-17-039496
• OSTI ID: 4630417
• Journal Information: Nuclear Science and Engineering (U.S.), Journal Name: Nuclear Science and Engineering (U.S.) Vol. Vol: 17; ISSN NSENA
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BOILING
CORROSION
DECOMPOSITION
FUEL CANS
HEAT TRANSFER
HIGH TEMPERATURE
HYDROGEN
MATERIALS TESTING
METALS, CERAMICS, AND OTHER MATERIALS
OXYGEN
RADIATION CHEMISTRY
RADIOLYSIS
REACTORS
STEAM
SUPERHEATING
WATER
WATER COOLANT