PROGRESS REPORT NO. 46 FOR APRIL AND MAY 1958

Technical Report · Mon Jun 16 04:00:00 EDT 1958

OSTI ID:4315378

Posey, W.J. ed.

The response characteristics of three chromel-alumel thermocouples to a ramp function change in temperature in the Bettis Foster Flow tube with the Core I seed cluster were determined. Experiments to obtain information on film boiling at elevated pressures in a forced-convection system were performed. The wnter parameters covered were: water inlet temperature 500 and 600 deg F, pressure 2000 psig, and mass flow rates 0.4 x 10/sup 6/ to 1.5 x 10/sup 6/ lb/hr- sq ft. Stress corrosion cracking of 304 stainless steel pipe by exposure to chloride-bearing water is being investigated. Fission product release and zirconium --water explosion hazards in core meltdown were evaluated by melting two zirconium-uranium subassemblies in a steam atmosphere. (For preceding period see NP-6661.) (W.D.M.)

• Research Organization: MSA Research Corp., Callery, Penna.
• NSA Number: NSA-12-011844
• OSTI ID: 4315378
• Report Number(s): NP-6787
• Country of Publication: United States
• Language: English

Related Subjects

ALUMEL
ALUMINUM ALLOYS
BOILING
CHEMICAL REACTIONS
CHLORIDES
CHROMEL
CHROMIUM ALLOYS
CONFIGURATION
CONTAMINATION
COOLANT LOOPS
CORROSION
CORROSION PROTECTION
CRACKS
EXPLOSIONS
FILMS
FISSION PRODUCTS
FLUID FLOW
HIGH TEMPERATURE
IMPURITIES
INERT GASES
LEAKS
MANGANESE ALLOYS
MATERIALS TESTING
MEASURED VALUES
MELTING
NICKEL ALLOYS
PHYSICS
PIPES
PRESSURE
PUMPS
REACTOR SAFETY
REACTORS
SILICIDES
STAINLESS STEELS
STEAM
STRESSES
TEMPERATURE
THERMAL STRESSES
THERMOCOUPLES
TUBES
URANIUM
WATER
WATER COOLANT
ZIRCONIUM