Published April 1991 | Version v1
Journal article

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 the ITER. It is found that the blanket can operate at moderate pressure and temperatures, which coupled to the use of ain 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 unofporm coolant exit temperature. Control of the pump pressure head ensures that the cooland temperature is kept below its maximum limit, set by the maximum allowable operating temperature of the breeder. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
126
Journal Issue
1
Series
Nucl. Eng. Des.
Journal Page Range
137-145
ISSN
0029-5493
CODEN
NEDEA

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
Netherlands
Country of Input or Organization
Netherlands
INIS RN
22078487
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BREEDING BLANKETS; COOLING; FLOW RATE; FRICTION FACTOR; GAS FLOW; HELIUM; ITER TOKAMAK; MASS TRANSFER; PRESSURE DEPENDENCE; PRESSURE DROP; TEMPERATURE DEPENDENCE; TRANSIENTS
Descriptors DEC
CLOSED PLASMA DEVICES; ELEMENTS; FLUID FLOW; NONMETALS; RARE GASES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

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