ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
R. Philip Hammond, John R. Humphreys, Jr.
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 421-425
Technical Paper | doi.org/10.13182/NSE64-A18759
Articles are hosted by Taylor and Francis Online.
This study considers a fast-reactor concept in which the recirculating molten plutonium alloy fuel is externally cooled by direct contact with an immiscible coolant fluid. An example of one such design is given using sodium as the coolant and Pu/Co/Ce ternary as the fuel. Operational characteristics are discussed showing the self-regulating features of the system. Some fission-product-removal mechanisms are considered together with their effect on core life and system safety. The principal problem areas are fuel pumping, phase separation, and containment-materials compatability.