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IAEA project aims to develop polymer irradiation model
The International Atomic Energy Agency has launched a new coordinated research project (CRP) aimed at creating a database of polymer-radiation interactions in the next five years with the long-term goal of using the database to enable machine learning–based predictive models.
Radiation-induced modifications are widely applicable across a range of fields including healthcare, agriculture, and environmental applications, and exposure to radiation is a major factor when considering materials used at nuclear power plants.
A. R. Raffray, F. Escourbiac, F. J. Fuentes, L. Giancarli, B. Macklin, A. Martin, M. Merola, R. Mitteau, J. Palmer
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 465-476
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-945
Articles are hosted by Taylor and Francis Online.
The overall programmatic objective of ITER is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes. The physics part of this objective (including burning plasma, Q of at least 10 and stationary conditions) seems to be well appreciated by the scientific community internationally. However, there seems to be less of an emphasis on the fusion technology part of the objective, which includes demonstrating the availability and integration of technologies essential for a fusion reactor and testing components including tritium breeding blanket modules for a future reactor. In fact important technology information will be obtained from the design, fabrication and operation of the vacuum vessel and out-of-vessel systems such as magnets, tritium system, cryogenic systems, cooling water systems, and associated safety aspects. In addition, DEMO-relevant information will be obtained from the operation of breeding blanket test modules in ITER. Moreover valuable information applicable to DEMO and beyond will also be obtained in a number of areas linked to in-vessel components. This paper summarizes the DEMO-relevant fusion technology information that will be obtained from ITER with a major focus on the areas linked to in-vessel components.