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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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November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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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.
M. Gardani, C. Ronchi
Nuclear Science and Engineering | Volume 107 | Number 4 | April 1991 | Pages 315-329
Technical Paper | doi.org/10.13182/NSE91-A23794
Articles are hosted by Taylor and Francis Online.
The transport and release of radioactive fission products in nuclear fuels are described with detailed reaction-rate equations including intragranular precipitation, radiation re-solution, biased diffusion, and nuclear transmutations. An analytical procedure is found to solve these equations that makes it possible to calculate the release and redistribution of the radionuclides with greater accuracy and with much more speed than conventional numerical methods. The method was implemented in the computer code MITRA for the calculation of the radionuclide behavior during stationary and nonstationary reactor operating conditions. The structure of this code is described, and recalculations of experiments are presented. The analytical solutions of the rate equations are reported in the Appendix.