A STUDY OF WET STEAM AS A REACTOR COOLANT. TECHNICAL PROGRESS REPORT FOR THE PERIOD APRIL 1, 1960 THROUGH DECEMBER 31, 1960

Technical Report · Tue Jan 31 04:00:00 EST 1961

OSTI ID:4069174

Sofer, G; Firstenberg, H; Hurwitz, S

Research and development investigations of water-steam mixtures under dispersed flow conditions (fog) and their applications to light-water-moderated nuclear power reactors are reported. The advantages of fog coolant are listed. Burn-out, heat transfer, and pressure drop data were obtained under fog-flow conditions at CISE. Localized flow measurements in the CISE test loop indicated that the slip ratio in the bulk of the flow stream is near unity. Corrosion tests in the loop indicated the absence of erosion effects in Zircaloy and stainless-steel specimens. Lowtemperature fog mixing tests indicated that the most effective mixer design is obtainable in a peripheral water injection arrangement. A theoretical investigation was made of burn-out heat transfer under fog flow conditions using a model based on eddy diffusion of droplets from the bulk of the flow stream to the heated wall. Nuclear calculation methods were developed and coded for Datatron computation to prevent more accurate calculation of reactivity effects. A conceptual reactor design, using fog as the coolant in a light-water-moderated reactor, is being developed. (M.C.G.)

• Research Organization: Nuclear Development Corp. of America, White Plains, N.Y.
• NSA Number: NSA-15-013926
• OSTI ID: 4069174
• Report Number(s): NDA-2132-4; EURAEC-102
• Country of Publication: United States
• Language: English

Related Subjects

BURNOUT
CISE
COMPUTERS
COOLANT LOOPS
COOLANTS
CORROSION
DIFFUSION
DISPERSIONS
EROSION
EUROPE
GAS FLOW
HEAT TRANSFER
HUMIDITY
IN PILE LOOPS
INJECTION
ITALY
PRESSURE
REACTIVITY
REACTOR TECHNOLOGY
REACTORS
STAINLESS STEELS
STEAM
TEMPERATURE
WATER
WATER COOLANT
WATER MODERATOR
WEAR
ZIRCALOY