Low technology high tritium breeding blanket concept

Conference · Thu Oct 01 04:00:00 EDT 1987

OSTI ID:5607521

Gohar, Y; Baker, C C; Smith, D L; Billone, M C; Cha, Y S; Clemmer, R; Finn, P A; Hassanein, A M; Johnson, C E; Liu, Y

The main function of this low technology blanket is to produce the necessary tritium for INTOR operation with minimum first wall coverage. The INTOR first wall, blanket, and shield are constrained by the dimensions of the reference design and the protection criteria required for different reactor components and dose equivalent after shutdown in the reactor hall. It is assumed that the blanket operation at commercial power reactor conditions and the proper temperature for power generation can be sacrificed to achieve the highest possible tritium breeding ratio with minimum additional research and developments and minimal impact on reactor design and operation. A set of blanket evaluation criteria has been used to compare possible blanket concepts. Six areas: performance, operating requirements, impact on reactor design and operation, safety and environmental impact, technology assessment, and cost have been defined for the evaluation process. A water-cooled blanket was developed to operate with a low temperature and pressure. The developed blanket contains a 24 cm of beryllium and 6 cm of solid breeder both with a 0.8 density factor. This blanket provides a local tritium breeding ratio of approx.2.0. The water coolant is isolated from the breeder material by several zones which eliminates the tritium buildup in the water by permeation and reduces the changes for water-breeder interaction. This improves the safety and environmental aspects of the blanket and eliminates the costly process of the tritium recovery from the water. 12 refs., 13 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5607521
• Report Number(s): CONF-871007-69; ON: DE88002883
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ALKALI METAL COMPOUNDS
ALKALINE EARTH METALS
BERYLLIUM
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
COOLING SYSTEMS
COST
DESIGN
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
FIRST WALL
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN ISOTOPES
INTOR TOKAMAK
INVENTORIES
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
MECHANICS
METALS
NUCLEI
ODD-EVEN NUCLEI
PERFORMANCE
PHYSICAL PROPERTIES
RADIOISOTOPES
REACTOR COMPONENTS
SAFETY
TECHNOLOGY ASSESSMENT
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES