Accession Number:

AD0724976

Title:

Heat Exchange and Hydromechanics of Dispersed through Flows (Selected Portions),

Descriptive Note:

Corporate Author:

FOREIGN TECHNOLOGY DIV WRIGHT-PATTERSON AFB OHIO

Personal Author(s):

Report Date:

1971-01-26

Pagination or Media Count:

15.0

Abstract:

The selected portion of a larger work deals with two types of nuclear reactors with dispersed through flows - those with an active solid component of the dispersed heat-transfer agent, and those with an inert component. Results of a 1957 study by the OTIL on the use of particles of artificial graphite as the dispersed component are discussed. The compatibility of the graphite with other properties and the high quality of its physical properties are stressed. A gas-graphite heat-transfer agent is seen as a very promising coolant for high-temperature nuclear reactors, and the prospect of gas-graphite flows also as a new working body in single-circuit nuclear devices is emphasized.

Subject Categories:

  • Fission Reactor Materials

Distribution Statement:

APPROVED FOR PUBLIC RELEASE