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Nuclear Engineering and Design 126 (1991) 137-145 137 North-Holland

Summary: Nuclear Engineering and Design 126 (1991) 137-145 137
Transient flow behavior for a helium-cooled ceramic breeder
blanket *
A.Y. Ying, A.R. Raffray and M.A. Abdou
Mechanical, Aerospace and Nuclear Engineering Department, Unioersity of California, Los Angeles, Los Angeles, CA 90024, USA
Received April 1990
This paper presents a thermal-hydraulic analysis of a helium-cooled ceramic breeder blanket for the ITER. It is found that
the blanket can operate at moderate pressure and temperatures, which coupled to the use of an inert gas, makes it particularly
attractive from a safety standpoint. Transient analysis of the manifolding flow distribution indicates that the introduction of a
diffusive plate at the inlet of the blanket coolant flow path produces a more uniform coolant exit temperature. Control of the
pump pressure head ensures that the coolant temperature is kept below its maximum limit, set by the maximum allowable
operating temperature of the breeder.
1. Introduction
The helium-cooled ceramic breeder blanket design
proposed for the International Thermonuclear Experi-
mental Reactor (ITER) and considered here consists of
blanket sectors outboard of the reactor, providing good
coverage of the torus surface [1]. As shown in fig. 1,
each sector comprises several independent blanket


Source: Abdou, Mohamed - Fusion Science and Technology Center, University of California at Los Angeles


Collections: Plasma Physics and Fusion