Conceptual design of a fission-based integrated test facility for fusion reactor components

Conference · Fri Jan 01 04:00:00 EST 1982

OSTI ID:5152966

Watts, K D; Deis, G A; Hsu, P Y.S.; Longhurst, G R; Masson, L S; Miller, L G

The testing of fusion materials and components in fission reactors will become increasingly important because of lack of fusion engineering test devices in the immediate future and the increasing long-term demand for fusion testing when a fusion reactor test station becomes available. This paper presents the conceptual design of a fission-based Integrated Test Facility (ITF) developed by EG and G Idaho. This facility can accommodate entire first wall/blanket (FW/B) test modules such as those proposed for INTOR and can also accommodate smaller cylindrical modules similar to those designed by Oak Ridge National laboratory (ORNL) and Westinghouse. In addition, the facility can be used to test bulk breeder blanket materials, materials for tritium permeation, and components for performance in a nuclear environment. The ITF provides a cyclic neutron/gamma flux as well as the numerous module and experiment support functions required for truly integrated tests.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5152966
• Report Number(s): EGG-M-05382; CONF-820406-22; ON: DE82018889
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
BREEDING BLANKETS
DESIGN
FIRST WALL
MATERIALS
MATERIALS TESTING
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
TEST FACILITIES
TEST REACTORS
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS