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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
M. Salvatores, I. Slessarev, M. Uematsu
Nuclear Science and Engineering | Volume 120 | Number 1 | May 1995 | Pages 18-39
Technical Paper | doi.org/10.13182/NSE95-A24103
Articles are hosted by Taylor and Francis Online.
This paper considers ways to approach radiologically clean nuclear power (RCNP), i.e., an energy production technology based on a natural nuclear fuel transmutation with a simultaneous fission product transformation into stable or short-lived nuclei. Ways to limit the long-term radiotoxicity accumulation in the fuel cycle, both related to actinides and to long-lived fission products, and to limit the radiological risk related to the in-core nuclear fuel inventory are defined. Criteria and guidelines are defined in that perspective, and they are applied to the evaluation of different options such as open or closed fuel cycles, burnup extension, type of neutron spectrum, use of thorium or uranium fuel cycle, and subcriticality in the multiplying region. Meanwhile, understanding the physics implications of the requirements for an RCNP reveals that there are promising ways to improve current systems. Ideal systems, which are defined to exploit all the desirable physics features to make them better in terms of environmental impact, show potential advantages, but they are never so spectacular—and certainly are to be taken extremely carefully—in view of the need of complementary technological feasibility and cost and safety analyses, Moreover, the problem of radiation doses, which is essential for fuel cycle management and could appreciably influence the choice of the appropriate fuel cycle, have not yet been taken into account. This last aspect and more specific safety analyses, together with cost-benefit evaluations, will be the subject of future investigations.