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Division Spotlight
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.
Meeting Spotlight
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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Fusion Science and Technology
Latest News
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
Anek Kumar, Umasankari Kannan, S. Ganesan
Nuclear Science and Engineering | Volume 194 | Number 1 | January 2020 | Pages 32-43
Technical Paper | doi.org/10.1080/00295639.2019.1645502
Articles are hosted by Taylor and Francis Online.
The general geometry continuous-energy Monte Carlo code M3C is currently under development at the Bhabha Atomic Research Centre for reactor physics calculations. The development of the Monte Carlo code M3C for reactor design entails the use of continuous-energy nuclear data and Monte Carlo simulations for each of the neutron interaction processes. This paper describes the current status of the development of the code. The performance and accuracy of the code in application to a variety of problems have been investigated. The important features of this code are treatment of heterogeneous lattices by general geometry, use of point cross sections along with unionized energy grid approach, thermal scattering model for low-energy treatment, probability table treatment in unresolved resonance range, and capability of handling the microscopic fuel particles (TRISO) dispersed randomly, which is very useful in modeling high temperature gas-cooled reactor fuels. Apart from all of the important features in any Monte Carlo code available worldwide, the M3C code has an advanced capability to handle the geometry, which is not described by mathematical equations but only represented by the geometrical points. The code has been validated for its accuracy against a large number of sample problems covering a wide range from simple (like spherical) to complex geometry (like pressurized heavy water reactor lattice) and including randomly dispersed TRISO fuel particle systems. The code is presently restricted to assembly-level calculations.