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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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Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
Kenta Inagaki
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 308-323
Research Article | doi.org/10.1080/00295450.2023.2239041
Articles are hosted by Taylor and Francis Online.
This paper presents simulation results of earlier fuel melting tests (xM3 and HBC4) performed under the power-to-melt-and-maneuverability (P2M) simulation exercise organized within the Organisation for Economic Co-operation and Development (OECD)/Nuclear Energy Agency (NEA) framework for irradiation experiments. The simulations were performed using the single-rod performance analysis code FRAPCON/FRAPTRAN as a contribution of the Central Research Institute of Electric Power Industry (CRIEPI) to the P2M simulation exercise. To this end, the base irradiation of each sample was simulated using FRAPCON software, and the calculated result was used to define the initial state of the transient simulations; the xM3 and HBC4 ramp tests were simulated using FRAPTRAN. Fuel melting was not predicted for xM3, and the melting radius was underestimated for HBC4 using the original version of FRAPTRAN. The value of the fuel/cladding gap conductance was modified to obtain results that satisfy the experimental measurement of the melting radius.
In this paper, the simulation results are compared with experimental results, and the causes for discrepancy between the simulation and experiment results are discussed. The necessary improvements for FRAPTRAN to achieve a better simulation of fuel melting are also discussed. These results can help calibrate codes against high-temperature behavior and improve fuel melting modeling toward the planned P2M power ramp tests.