AXIAL MIDPOINT SPACERS IMPROVE EGCR HEAT TRANSFER

Journal Article · Mon Jan 01 04:00:00 EST 1962 · Nuclear Eng.

OSTI ID:4817562

Higgins, R M; McDonald, T J

A description is given of four types of axial midpoint spacer sets that may improve the heat transfer charac teristics of gas cooled reactor fuel elements. A test apparatus is described which duplicates the flow geometry of the proposed fuel assemblies for the Experimental Gas Cooled Reactor (EGCR). Each EGCR fuel assembly consists of a cluster of seven stainless steel tubes filled with urania pellets mounted inside a cylindrical graphite sleeve. The axis of one tube coincides with the sleeve axis; the other six tubes are equally spaced around the central tube. Each outer tube spacer has vanes (either straight or helical) and a single projecting pad. The vanes prevent tubes from touching each other; the pads prevent tubes from touching the sleeve. Central tube spacers do not have pads. The heat transfer characteristics of each type of spacer is given. An analytical correction is applied to account for the circumferential conduction of heat away from the high temperature areas through the tube material. (N.W.R.)

• Research Organization: Allis-Chalmers Mfg. Co., Washington, D.C.
• NSA Number: NSA-16-008381
• OSTI ID: 4817562
• Journal Information: Nuclear Eng., Journal Name: Nuclear Eng. Vol. Vol: 7
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

CONFIGURATION
COOLANT LOOPS
CYLINDERS
EFFICIENCY
EGCR
FUEL CANS
FUEL ELEMENTS
GAS COOLANT
GRAPHITE
GRAPHITE MODERATOR
HEAT TRANSFER
HIGH TEMPERATURE
MECHANICAL STRUCTURES
PELLETS
PLANNING
POWER PLANTS
REACTOR CORE
REACTOR TECHNOLOGY
SPACERS
STAINLESS STEELS
SURFACES
THERMAL CONDUCTIVITY
TUBES
ZONES