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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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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
NRC’s Inspector General issues report
Overall findings of a survey of Nuclear Regulatory Commission personnel indicate that while the NRC maintains a few strengths compared to external benchmarks, results have declined since 2015 in a number of areas, according to a recent report from the NRC’s Office of the Inspector General (OIG).
The survey was conducted in February 2020 by Willis Towers Watson, a global risk-management, insurance brokerage, and advisory firm that has partnered with the OIG for more than 20 years to assess the NRC’s safety culture and climate, as well as other aspects of employee experience.
K.E. Plute, E.M. Larsen, L.C. Wittenberg, D.K. Sze
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 407-411
Tritium | dx.doi.org/10.13182/FST83-A22898
Articles are hosted by Taylor and Francis Online.
Various techniques for tritium removal from the liquid eutectic Li17Pb83 under vacuum are considered as candidates for the tritium removal system (TRS) for the Mirror Advanced Reactor Study (MARS). The TRS baseline parameters require the removal of 60% of the tritium contained in the liquid metal at a tritium partial pressure of 1.0 × 10−4 torr (0.013 Pa). Degassing from a droplet spray was chosen as the preferred design option, although removal from thin films is a feasible alternative. Vacuum removal from a stirred pool was rejected because of the size and relatively poor transport conditions. The use of an inert purge gas was also rejected due to the large purge gas flow rate and the problem of separating tritium from a large quantity of inert gas.
