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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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June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
Rainer Köster, Günter Rudolph
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 192-201
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT91-A34605
Articles are hosted by Taylor and Francis Online.
The release of radionuclides from a waste form into an aqueous phase is often assessed using a source term that considers diffusion and/or congruent matrix dissolution as the rate-determining release mechanisms. As an alternative approach, an equilibrium concept is proposed here that can be applied under the condition that there is no appreciable exchange of fluid with the environment of the waste package / form after the water inflow into the near field for a long time. In this case, all reactions that may give rise to radionuclide release will be completed after a certain time and stable final conditions will be established, in which, for each radionuclide, chemical equilibria exist between the dissolved phase and the various coexisting solid phases. Thereafter, a release of radionuclides from the near field is possible only by escape of the aqueous phase into the environment. Release rate predictions on the basis of this concept are of particular interest for the long-lived radionuclides, especially the actinides. Current efforts are aimed at predicting equilibrium concentrations both in theoretical computations and in experimental measurements. Some results available from corrosion studies on cemented waste forms in salt brine are presented. For specimens doped with cesium, strontium, plutonium, or americium these results show that for each radionuclide a partition equilibrium exists between the corrosion products of cement and the surrounding salt brine, which keeps the concentration in solution at a low level.