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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.
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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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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.
William J. Westlake, Jr., A. F. Henry
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 482-488
Technical Paper | doi.org/10.13182/NSE72-A22567
Articles are hosted by Taylor and Francis Online.
A method is proposed for treating depletion effects in a nuclear reactor by a mathematical model in which the time derivative of the neutron flux is retained and the reactor is kept at its desired power level through operation of a control system actuated by any differences between the actual and desired power level. The criticality searches required with the conventional depletion method to find consistent density-temperature profiles, control rod positions, xenon distribution, and flux shapes are thereby avoided. The time-dependent flux, control, and isotopic concentration equations are linearized and solved simultaneously by a numerical procedure that permits time steps as large as those employed with conventional depletion codes. Simple numerical examples that test the essential features of the method are presented.