Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

US Demo test blankets in ITER

Journal Article · · Fusion Technology
OSTI ID:449160
;  [1]; ;  [2]; ;  [3];  [4]
  1. McDonnell Douglas Aerospace, St. Louis, MO (United States)
  2. Univ. of California, Los Angeles, CA (United States)
  3. Argonne National Lab., IL (United States)
  4. Rockwell International Corp., Canoga Park, CA (United States)

This paper summarizes the current status of the Demo blanket test systems and how the ITER reactor design and operations are being accommodated. The US blanket program is planning to develop a liquid metal breeder and a solid breeder blanket for testing and evaluation. The test blanket modules will have prototypical components, materials, and coolants representative of power reactor systems. The modules are to be located in the ITER horizontal test ports and installed/removed with special remote handling equipment. Adjacent ITER blanket neutronic and temperature conditions suggest the use of an isolation frame surrounding the test blanket modules or submodules. This frame will also provide additional shielding to protect the adjacent vacuum vessel. The frame and blanket module are attached to the surrounding backplate to transfer static and dynamic loads. All coolants and tritium-bearing fluids will be routed out of the midplane port to special heat exchangers and tritium separation systems. Special remote handling equipment is being designed to install and extract the test blanket modules. Dedicated transporters will be used to move the blanket and shielding modules to dedicated hot cells. Special facility areas will be provided immediately outside the port areas for the heat exchangers, pumps, and tritium-separation systems. 1 ref., 6 figs.

OSTI ID:
449160
Report Number(s):
CONF-9606116--
Journal Information:
Fusion Technology, Journal Name: Fusion Technology Journal Issue: 3 Vol. 30; ISSN 0748-1896; ISSN FUSTE8
Country of Publication:
United States
Language:
English