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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.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
Mofassir Ud Dowla, M. A. Rashid Sarkar (Bangladesh Univ of Eng and Technology)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 523-532
This paper illustrates numerical simulations of heat transfer and fluid flow in triangular section and unit cell section of fuel blocks of High Temperature Gas-cooled Reactor (HTGR). The thermal hydraulic simulations have been performed in a minimalistic computational resource environment and their viabilities have been studied. General Atomics Modular High Temperature Gas-cooled Reactor (MHTGR) has been considered in this work as a reference design. In this paper, 3-D models of triangular section and unit cell section of fuel blocks similar to the MHTGR design have been developed for single phase helium flow using COMSOL Multiphysics software. In these models, velocity profiles, temperature profiles, pressure profiles, Reynolds number profiles and Nusselt number profiles have been studied. Algebraic y+ turbulence model has been used in this work. Finally, the simulation results have been compared with General Atomics provided MHTGR design parameters and theoretically obtained results to check for their accuracy and viability.