Preconceptual design and analysis of a solid-breeder blanket test in an existing fission reactor

Conference · Sat Jan 01 04:00:00 EST 1983

OSTI ID:5115333

Deis, G A; Hsu, P Y; Watts, K D

Preconceptual design and analysis have been performed to examine the capabilities of a proposed fission-based test of a water-cooled Li/sub 2/O blanket concept. The mechanical configuration of the test piece is designed to simulate a unit cell of a breeder-outside-tube concept. This test piece will be placed in a fission test reactor, which provides an environment similar to that in a fusion reactor. The neutron/gamma flux from the reactor produces prototypical power density, tritium production rates, and operating temperatures and stresses. Steady-state tritium recovery from the test piece can be attained in short-duration (5-to-6-day) tests. The capabilities of this test indicate that fission-based testing can provide important near-term engineering information to support the development of fusion technology.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5115333
• Report Number(s): EGG-M-10783; CONF-831203-114; ON: DE84005053
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BREEDING BLANKETS
DATA ANALYSIS
DESIGN
ELECTROMAGNETIC RADIATION
FISSION
GAMMA RADIATION
IONIZING RADIATIONS
MATERIALS TESTING
NEUTRON FLUX
NONDESTRUCTIVE TESTING
NUCLEAR REACTIONS
RADIATION FLUX
RADIATIONS
REACTOR COMPONENTS
REACTORS
SIMULATION
STEADY-STATE CONDITIONS
TEST FACILITIES
TESTING
THERMAL TESTING
WATER COOLED REACTORS