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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Crash Course: The DOE’s Package Performance Demonstration
Inspired by a history of similar testing endeavors and recommended by the National Academy of Sciences and the Blue Ribbon Commission on America’s Nuclear Future, the Department of Energy is planning to conduct physical demonstrations on rail-sized spent nuclear fuel transportation casks. As part of the project, called the Spent Nuclear Fuel Package Performance Demonstration (PPD), the DOE is considering a number of demonstrations based on regulatory tests and realistic transportation scenarios, including collisions, drops, exposure to fire, and immersion in water.
M. Corradini
Nuclear Technology | Volume 181 | Number 1 | January 2013 | Pages 2-10
Technical Paper | Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics | doi.org/10.13182/NT13-A15752
Articles are hosted by Taylor and Francis Online.
Nuclear power plants are currently operating throughout the world and are supplying more than one-sixth of the world's electricity. In spite of recent events in Japan, given the current rate of growth in electricity demand and the ever growing concerns for the environment, nuclear power remains a key technology that can help satisfy the need for electricity and other energy products if it can demonstrate (a) enhanced system reliability and safety, (b) minimal environmental impact via sustainable system designs, and (c) competitive economics. Since 2000, the United States in collaboration with the international community has begun research on the next generation of nuclear energy systems that can be made available to the market over the next couple of decades and may offer significant advances toward these challenging goals. For near-term deployment, advanced water-cooled thermal reactors are being ordered or are under construction. Beyond this next decade, there are future nuclear power systems [so-called Generation IV (Gen IV)] that require advances in materials, reactor physics, and heat transfer to realize their potential. In particular, the use of supercritical fluids in Gen IV nuclear systems has gained prominence. The focus of this paper is to summarize some of the key supercritical heat transfer topics that we are addressing to assure appropriate reliable design and operation of these advanced nuclear systems.