A module for testing a lithium cooled tokamak blanket in a tandem mirror test reactor

Conference · Mon Jul 01 00:00:00 EDT 1985 · Fusion Technol.; (United States)

OSTI ID:5876626

Garner, J K; Blanchard, J; Madarame, H; Orient, G; Shin, K; Taghavi, K; Tillack, M; Youssef, M

A preliminary conceptual design was made of a test module for testing the BCSS lithium cooled, vanadium structure blanket concept in a tandem mirror fusion test reactor. The test module is intended to run at the correct stresses and temperatures of a segment of the blanket, while operating at reduced neutron wall loadings. Although this approach ties the effort to a single design and its issues, it tends to reveal interactions that might not be apparent if a more general approach were taken, and can lead to some useful general conclusions.

• Research Organization: TRW, Redondo Beach, CA
• OSTI ID: 5876626
• Report Number(s): CONF-850310-
• Journal Information: Fusion Technol.; (United States), Vol. 8:1; Conference: 6. topical meeting on the technology of fusion energy, San Francisco, CA, USA, 3 Mar 1985
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
MATERIALS TESTING
PERFORMANCE TESTING
TEST FACILITIES
DESIGN
TMR REACTORS
TOKAMAK TYPE REACTORS
LITHIUM
NEUTRON FLUENCE
STRESSES
TEMPERATURE EFFECTS
TEST REACTORS
VANADIUM
WALL LOADING
ALKALI METALS
ELEMENTS
MAGNETIC MIRROR TYPE REACTORS
METALS
POWER DENSITY
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
TESTING
THERMONUCLEAR REACTORS
TRANSITION ELEMENTS
700201* - Fusion Power Plant Technology- Blanket Engineering
700209 - Fusion Power Plant Technology- Component Development & Materials Testing