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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
V. Chuyanov, ITER International Team
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 469-474
Technical Paper | Fusion Energy - First Wall, Blanket, and Shield | doi.org/10.13182/FST05-A731
Articles are hosted by Taylor and Francis Online.
One of the objectives of ITER is to demonstrate fusion technology in an integrated system by performing testing of nuclear components, in particular to test design concepts of tritium breeding blanket relevant to a DEMO reactor. In the current ITER design three large equatorial ports have been allocated for blanket module testing.Typical testing conditions foreseen now include a surface heat flux of 0.1 MW/m2, a neutron wall load of 0.78 MW/m2, pulse length of 400 s with a duty cycle of 25%. After the first 10 years of operation one may expect to reach a total neutron fluence at the surface of test blanket modules ~ 0.12 Mwy/m2. In the second 10 years of operation very long pulses and accumulation of neutron fluence ~ 0.3 MWy/m2 may be expected.Test modules must not compromise ITER safety and reliability. Water-cooled modules must have their own pressure suppression system. The mass of liquid lithium is strictly limited to avoid a hydrogen explosion.Breeding blanket testing in ITER is extremely important for DEMO breeding blanket development. The best effort has to be undertaken to coordinate the Parties' activities in this area and to achieve the best use of space and time available for blanket testing in ITER.
