Published 1989 | Version v1
Book

Transient flow behavior for a helium-cooled ceramic breeder blanket

  • 1. California Univ., Los Angeles (USA). Dept. of Mechanical, Aerospace and Nuclear Engineering

Description

This paper presents a thermal-hydraulic analysis of a helium-cooled ceramic breeder blanket for ITER. It is found that the blanket can operate at moderate pressure and temperature, which coupled to the use of an inert gas, makes it particularly attractive from a safety stand point. 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. (orig.)

Additional details

Publishing Information

Publisher
Braun.
Imprint Place
Karlsruhe (Germany, F.R.)
ISBN
3-7650-1116-9
Imprint Title
Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 2
Imprint Pagination
696 p.
Journal Page Range
p. 878-883.

Conference

Title
4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
Dates
10-13 Oct 1989.
Place
Karlsruhe (Germany, F.R.).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
22035955
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BREEDING BLANKETS; CERAMICS; FLOW RATE; GAS COOLING; HELIUM; HYDRAULICS; ITER TOKAMAK; LITHIUM SILICATES; PRESSURE DROP
Descriptors DEC
ALKALI METAL COMPOUNDS; CLOSED PLASMA DEVICES; COOLING; ELEMENTS; LITHIUM COMPOUNDS; NONMETALS; OXYGEN COMPOUNDS; RARE GASES; SILICATES; SILICON COMPOUNDS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Contract/Grant/Project number
Contract DE-FG03-86ER52123