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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.
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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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Fusion Science and Technology
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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Kusuma Dewi, Akira Hasegawa, Satoshi Otsuka, Katsunori Abe
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 585-589
Fusion Materials | doi.org/10.13182/FST01-A11963300
Articles are hosted by Taylor and Francis Online.
In ITER, austenitic stainless steels are under consideration as a blanket structural material for temperature below 200°C. Transmuted helium will be also produced in austenitic stainless steels by high-energy neutron irradiation, and it will affect microstructural development including grain boundary segregation. In this paper, the effects of helium on grain boundary segregation in austenitic stainless steels are studied using ion-irradiation experiment.
The result showed that the onset of radiation induced segregation (RIS) by proton irradiation occurs somewhere between 0.1 and 0.5 dpa. Helium pre-implantation significantly reduced RIS of the major alloying elements. Mechanisms are discussed. Comparison of this result with neutron irradiated induced segregation showed qualitative agreement in the data trends. However, a large amount of segregation was observed in the proton irradiated 304 austenitic stainless steels specimens.
