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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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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.
Jin-Yang Li, Long Gu, Hu-Shan Xu, Yong Dai, You-Peng Zhang, Cun-Feng Yao, Rui Yu, Lu Zhang, Sheng Yang
Nuclear Technology | Volume 207 | Number 2 | February 2021 | Pages 270-284
Technical Paper | doi.org/10.1080/00295450.2020.1757963
Articles are hosted by Taylor and Francis Online.
To study the burnup features of accelerator-driven subcritical systems (ADSs), simplified transmutation trajectories are imperative to make the simulation process more effective with acceptable precision. This process has long been considered a challenging task since the construction of simplified burnup chains often need complex judgments and experiences. Additionally, the burnup analysis of ADSs requires more specific burnup chains for some important isotopes with minor actinides (MAs) and long-lived fission products (LLFPs) included. However, some general burnup codes lack these chains or pack some particularly important isotopes into a kind of pseudo nuclide. In this context, a PyNE-based burnup module (PyNE-Burn) has been developed to solve the burnup problem in ADSs, where three types of isotopes have been considered to construct the simplified burnup chains and weight-sorted judgment criteria have been proposed to determine which nuclides should be included. Moreover, the scan-mode-method-based high-order differential expression has been employed to substitute the legacy method in solving the linearized burnup chains. Finally, numerical tests have been carried out to demonstrate that the PyNE-Burn module has acceptable accuracy and can be used in dealing with the burnup problem in ADSs.