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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Three nations, three ways to recycle plastic waste with nuclear technology
Plastic waste pollutes oceans, streams, and bloodstreams. Nations in Asia and the Pacific are working with the International Atomic Energy Agency through the Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative to tackle the problem. Launched in 2020, NUTEC Plastics is focused on using nuclear technology to both track the flow of microplastics and improve upstream plastic recycling before discarded plastic can enter the ecosystem. Irradiation could target hard-to-recycle plastics and the development of bio-based plastics, offering sustainable alternatives to conventional plastic products and building a “circular economy” for plastics, according to the IAEA.
C. F. Baes, Jr., R. P. Wichner, C. E. Bamberger, B. F. Freasier
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 399-410
Technical Paper | doi.org/10.13182/NSE75-A26685
Articles are hosted by Taylor and Francis Online.
The results of experiments in which iodine, dissolved as I- in LiF-BeF2 melts, was stripped as HI by sparging with HF-H2 mixtures have indicated that it may be possible to use such treatment to remove iodine from the molten fluoride mixtures used in molten salt reactor (MSR) fuels. This is of particular significance to MSR technology because it indirectly provides the means for removing a significant fraction of 135Xe, a decay daughter of 135I. Data obtained from transpiration experiments indicated a linear decrease of the logarithm of the iodine concentration of the melt with the number of moles of HF passed, and a linear increase of the reciprocal of the apparent equilibrium quotient Q'app = PHI/ (PHF [I-]) with the partial pressure of HF in the sparge gas. The iodine removal mechanism is explained by a model which assumes that the rate-controlling step is the transport of I- from the bulk of the melt to the surface and that the rates of the other steps are rapid. The removal of iodine from a molten salt breeder reactor (MSBR) fuel was analyzed in terms of the redox potential required to remove the iodine efficiently while preventing undesirable reactions in the fuel or between the fuel and its environment. The relative abundances of different iodine species present in the off-gas during sparging of an MSBR fuel were estimated; as expected, the results indicated a strong dependence on the temperature and hydrogen partial pressure. Low hydrogen pressures and low temperatures favor the formation of molecular iodine. High temperatures and low hydrogen pressures favor the formation of atomic iodine, while HI is formed at high temperatures and relatively higher hydrogen pressures.