Published March 1989
| Version v1
Journal article
An aqueous lithium salt self-cooled blanket and shield for ITER
- 1. Univ. of Wisconsin, Madison, WI (USA)
Description
A low cost low risk tritium breeding concept has been developed for ITER. This concept is based on dissolving lithium compounds in the water coolant. This makes it possible to breed tritium in all the shield zones, and results in tritium self-efficiency as well as enhanced magnet protection. The design that maximizes the outboard tritium breeding ratio utilizes a 40 cm thick zone of Be balls followed by an 80 cm thick zone of steel balls. Single size balls are used to minimize the pressure drop. The overall TBR excluding tritium bred in the test modules is 1.1. The inlet coolant temperature is 400C and the temperature rise is 150C in the first wall and 350C in the blanket
Additional details
Publishing Information
- Journal Title
- Fusion Technology
- Journal Volume
- 15
- Journal Issue
- 2
- Series
- Fusion Technol.
- Journal Page Range
- 643-648
- ISSN
- 0748-1896
- CODEN
- FUSTE
Conference
- Title
- 8. topical meeting on technology of fusion energy.
- Dates
- 9-13 Oct 1988.
- Place
- Salt Lake City, UT (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20054238
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BERYLLIUM; BREEDING BLANKETS; BREEDING RATIO; EXPERIMENTAL REACTORS; FIRST WALL; LITHIUM COMPOUNDS; MINIMIZATION; PRESSURE DROP; SHIELDS; SPECIFICATIONS; STEELS; TEMPERATURE GRADIENTS; TRITIUM PRODUCTION REACTORS
- Descriptors DEC
- ALKALI METAL COMPOUNDS; ALKALINE EARTH METALS; ALLOYS; CARBON ADDITIONS; CONVERSION RATIO; ELEMENTS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; METALS; OPTIMIZATION; REACTORS; RESEARCH AND TEST REACTORS; THERMONUCLEAR REACTOR WALLS
Optional Information
- Secondary number(s)
- CONF-881031--.