Published March 1995 | Version v1
Journal article

ITER shielding blanket

  • 1. ENTEK, Moscow (Russian Federation)
  • 2. NIAT, Moscow (Russian Federation)
  • 3. KIAE, Moscow (Russian Federation)
  • 4. DYNAMICA, Moscow (Russian Federation)

Description

A reference non-breeding blanket is under development now for the ITER Basic Performance Phase for the purpose of high reliability during the first stage of ITER operation. More severe operation modes are expected in this stage with first wall (FW) local heat loads up to 100-300Wcm-2. Integration of a blanket design with protective and start limiters requires new solutions to achieve high reliability, and possible use of beryllium as a protective material leads to technologies. The rigid shielding blanket concept was developed in Russia to satisfy the above-mentioned requirements. The concept is based on a copper alloy FW, austenitic stainless steel blanket structure, water cooling. Beryllium protection is integrated in the FW design. Fabrication technology and assembly procedure are described in parallel with the equipment used. (orig.)

Additional details

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
27
Journal Page Range
p. 363-371.
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
3. international symposium on fusion nuclear technology (ISFNT-3).
Dates
26 Jun - 1 Jul 1994.
Place
Los Angeles, CA (United States).