Water-cooled solid-breeder concept for ITER
Conference
·
OSTI ID:6642749
A water-cooled solid-breeder blanket concept was developed for ITER. The main function of this blanket is to produce the necessary tritium for the ITER operation. Several design features are incorporated in this blanket concept to increase its attractiveness. It is assumed that the blanket operation at commercial power reactor conditions can be sacrificed to achieve a high tritium breeding ratio with minimum additional research and development, and minimal impact on reactor design and operation. Operating temperature limits are enforced for each material to insure a satisfactory blanket performance. In fact, the design was iterated to maximize the tritium breeding ratio and satisfy these temperature limits. The other design constraint is to permit a large increase in the neutron wall loading without exceeding the temperature limits for the different blanket materials. The blanket concept contains 1.8 cm of Li/sub 2/O and 22.5 cm of beryllium both with a 0.8 density factor. The water coolant is isolated from the breeder material by several zones which reduces the tritium buildup in the water by permeation, reduces the chance for water-breeder interaction, and permits the breeder to operate at high temperature with a low temperature coolant. This improves the safety and environmental aspects of the blanket and eliminates the costly process of the tritium recovery from the water. The key features and design analysis of this blanket are summarized in this paper. 11 refs., 2 figs., 3 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6642749
- Report Number(s):
- CONF-881031-39; ON: DE89003593
- Country of Publication:
- United States
- Language:
- English
Similar Records
Water-cooled solid-breeder blanket concept for ITER
Low technology high tritium breeding blanket concept
Solid breeder blanket option for the ITER conceptual design
Conference
·
Tue Feb 28 23:00:00 EST 1989
· Fusion Technol.; (United States)
·
OSTI ID:6244715
Low technology high tritium breeding blanket concept
Conference
·
Thu Oct 01 00:00:00 EDT 1987
·
OSTI ID:5607521
Solid breeder blanket option for the ITER conceptual design
Conference
·
Sun Oct 01 00:00:00 EDT 1989
·
OSTI ID:5292473
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
COOLING SYSTEMS
DESIGN
ENERGY SYSTEMS
FIRST WALL
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
COOLING SYSTEMS
DESIGN
ENERGY SYSTEMS
FIRST WALL
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES