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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
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.