Published April 1991
| Version v1
Journal article
Transient flow behavior for a helium-cooled ceramic breeder blanket
Creators
- 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