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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
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
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Sung Ho Lee, Geun Il Park, Sung Bin Park
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 167-173
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-87
Articles are hosted by Taylor and Francis Online.
Pyroprocessing technology is one of the most promising technologies for many advanced fuel cycle scenarios with favorable economic potential and intrinsic proliferation resistance. In pyroprocessing technology, the development of high-temperature transport technologies for molten salt is a crucial prerequisite and a key issue in the industrialization of pyroreprocessing. However, there have been a few transport studies on high-temperature molten salt. Three different salt transport technologies (gravity, suction pump, and centrifugal pump) were investigated to select the most suitable method for LiCl-KCl molten salt transport. The suction pump transport method was selected for molten salt transport owing to its flexibility. An apparatus for suction transport experiments was designed and installed for the development of high-temperature molten salt transport technology. Several preliminary suction transport experiments were carried out using the prepared LiCl-KCl eutectic salt at 773 K to observe the transport behavior of LiCl-KCl molten salt. For the experiments, ∼2 kg of LiCl-KCl eutectic salt was prepared by mixing 99.0% purity LiCl and KCl and drying in a convection dry oven at 473 K for 1 h. The experimental results of a laboratory-scale molten salt transport using a suction method showed a 99.5% transport rate (ratio of transported salt to total salt) under a vacuum range of 0.0133 to 1.33 kPa at 773 K. From experimental results on the mass flow rate according to suction transport time, the mass flow rate according to suction time is 1.54 kg/min. In addition, to establish engineering-scale salt transport technology, the PRIDE salt transport system was designed and installed in an Ar cell, on the second floor of the PRIDE facility, for engineering-scale salt transport demonstration, and its performance was confirmed.