Published December 1999 | Version v1
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Suitability and feasibility of the international fusion materials irradiation facility (IFMIF) for fusion materials studies

  • 1. EURATOM-FZK Association, Forschungszentrum Karlsruhe, IMF-I, Karlsruhe (Germany)
  • 2. University of Tennessee, Knoxville, TN (United States)
  • 3. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
  • 4. Los Alamos National Laboratory, Los Alamos, NM (United States)
  • 5. Tokohu University, Dept. of Machine Intelligence and System Engineering, Sendai (Japan)
  • 6. JAERI, Tokai-mura, Ibaraki-ken (Japan)
  • 7. ENEA-CR Frascati, Frascati (Italy)
  • 8. Institute for High Energy Physics, Protvino (Russian Federation)

Description

There is a global consensus among materials scientists and engineers that the qualification of materials in an appropriate test environment is inevitable for design, construction and safe operation of DEMOnstration fusion reactors as well as for calibration of data generated from fission reactor and accelerators irradiations. In an evaluation process based on a series of technical workshops it was concluded that an accelerator driven D-Li stripping source would be the best choice to fulfill the requirements within a realistic time frame. In response to this need, an international design team with members from Europe, Japan, USA and Russia has developed under the auspices of the IEA during a Conceptual Design Activity Phase (1994-96) a suitable and feasible concept for an accelerator driven D-Li stripping source. This IFMIF reference design is based on conservative linac technology and two parallel operating 125-mA, 40-MeV deuteron beams that are focused onto a common liquid lithium target with a beam footprint of 50 mm by 200 mm. The materials testing volume downstream the Li-target is subdivided into different flux regions: The high flux test region (0.5 liter, 20-55 dpa/full power year), the medium flux test region (6 liter, 1-20 dpa/fpy), and low flux test regions (>100 liter, < 1 dpa/fpy). The developed design was the basis fore the present Conceptual Design Evaluation Phase (1997-98) and for subsequent engineering oriented activities. Based on comprehensive neutron transport calculations, an evaluation of the irradiation parameters and the available test volumes has shown that the users requirements can be fulfilled. Major engineering efforts have been undertaken to establish an IFMIF design that is based on available and already proven technologies. The developed design includes extensive reliability, availability, maintainability as well as safety studies and is conceived for long-term operation with a total annual facility availability of at least 70%. (author)

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Part of:
Fusion energy 1998. Proceedings. V. 1-4

Additional details

Publishing Information

Imprint Title
Fusion energy 1998. Proceedings. V. 1-4
Imprint Pagination
1721 p.
Journal Issue
no. 1/P
Series
C and S papers series
Journal Page Range
v. 3 p. 1203-1210
ISSN
1563-0153
Report number
IAEA-CSP--1/P

Conference

Title
17. IAEA fusion energy conference
Dates
18-24 Oct 1998
Place
Yokohama (Japan)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
31011456
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FIRST WALL; IRRADIATION DEVICES; MAGNETIC CONFINEMENT; MEETINGS; PHYSICAL RADIATION EFFECTS; THERMONUCLEAR REACTOR MATERIALS
Descriptors DEC
CONFINEMENT; MATERIALS; PLASMA CONFINEMENT; RADIATION EFFECTS; THERMONUCLEAR REACTOR WALLS

Optional Information

Notes
14 refs, 4 figs, 2 tabs
Secondary number(s)
FT2--4