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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
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
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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Latest News
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.
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.