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The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Fusion Science and Technology
Latest News
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.
F. Cismondi, G. Aiello, S. Kecskes, G. Rampal
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 123-127
ITER Systems | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12338
Articles are hosted by Taylor and Francis Online.
Six different breeding blanket concepts will be tested in ITER under the form of six different Test Blanket Modules (TBMs). In the frame of the activities of the European TBM Consortium of Associates the Helium Cooled Pebble Bed (HCPB-TBM) and the Helium Cooled Lithium Lead (HCLL) Test Blanket Modules are developed in Karlsruhe Institute of Technology (KIT) and in CEA Saclay respectively. For each EU TBM concept, four different TBMs will be installed into one dedicated ITER equatorial port and tested during different test campaigns. The main goal of the ITER TBM program is providing DEMO relevant experimental data for the three main functions of a blanket module of a future fusion reactor, namely removing heat, breeding tritium and shielding sensitive components from radiation.The two EU TBMs share a common external structure (the so called TBM box) while featuring a different internal design of the Breeder Units (BUs), reflecting the different breeding concept. The preliminary design assessment of the two TBMs boxes is based on nuclear analyses and on the evaluation of the power produced in the BU and deposed on the TBM box structures. The preliminary thermomechanical designs have been presented and are based on steady state analyses.The TBMs will work under ITER loads, i.e. cyclic loads defined by the typical ITER pulses. Transient thermal and mechanical analyses of the two EU TBMs under a typical ITER pulse are presented in this paper, identifying the main design issues related to: structural behavior of the TBM box, codes and standard rules for assessing the TBM box integrity, TBM operational domain and related DEMO relevancy of the experimental campaign. Solutions to improve the weak structural points of the present designs are proposed, identifying the missing rules and the modelling development needs.