EFFECT OF ROD SPACING ON HEAT TRANSFER BURNOUT. USAEC-AECL Co-operative Program Monthly Progress Report, September 1963

Technical Report · Fri Nov 01 04:00:00 EST 1963

OSTI ID:4144171

Towell, R H

A program was undertaken to determine some of the operating conditions of heavy-water-moderated power reactors. A practicable reactor would contain a minimum amount of light water poison in the fuel coolant channels. This can be achieved by operating with closely spaced fuel rods and high outlet steam qualities. The effects of these variables on the heat transfer and hydraulic characteristics of rod bundles are being studied. Measurements of the heat transfer coefficient, burnout heat flux, and pressure drop will be made on a 4- foot-long mockup of the central rod and 6 intermediate rods of a 19-rod bundle. Steam quality will be varied up to about 60% and mass flow up to about 5.0 x 10/ sup 6/ lb/(hr)(ft/sup 2/). The effects of spacers and both vertical and horizontal orientation of the test section will also be determined. The 6- intermediate-rod mockup was shipped for plating. Preliminary skakedown tests were continued with the annular housing tube in place of the 6-intermediate-rod mockup. These tests indicated two additional equipment changes are necessary to minimize bowing of the central rod. (auth)

• Research Organization: Du Pont de Nemours (E.I.); Co. Savannah River Lab., Aiken, S.C.
• NSA Number: NSA-18-003172
• OSTI ID: 4144171
• Report Number(s): DPST-63-69-10
• Country of Publication: United States
• Language: English

Related Subjects

ABSORPTION
BURNOUT
CONFIGURATION
COOLANT LOOPS
FUEL ELEMENTS
HEAT TRANSFER
HEAVY WATER MODERATOR
HYDRAULICS
MECHANICAL STRUCTURES
MOCKUP
OPERATION
PLATING
POISONING
POWER PLANTS
QUANTITATIVE ANALYSIS
REACTOR TECHNOLOGY
REACTORS
RODS
SPACERS
STEAM
TUBES
WATER