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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
J. Prij
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 100-109
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT96-A35202
Articles are hosted by Taylor and Francis Online.
High-level radioactive waste (HLW) contains nuclides that present a potential risk for man and the environment for a very long time—up to many thousands of years. Worldwide research activities are directed toward establishing how HLW can be safely disposed in stable geological formations such as rock salt formations. The unusual timescale of the problem has given rise to public and scientific concern about the reliability and the longevity of the proposed solutions. This has led to many suggestions about mechanisms that might provide a pathway for the nuclides to reach the biosphere. Although some of these suggestions are rather far fetched, disregarding them without thorough and scientifically sound argumentation is considered unacceptable. This paper should be viewed in this light. The disposal of HLW in a salt formation will result in the deposit of gamma energy in the rock salt. Most of this energy will be converted into heat while a small part will create defects in the salt crystals. It has been shown that energy is stored in the defected crystals. Because of uncertainties in the models and differences in the disposal concepts, the estimated values for the stored energy range from 10 to 1000 J/g in the most heavily defected crystals close to the waste containers. Given the uncertainties in the model predictions and in the possible release mechanism, this paper concludes that at this moment, an instantaneous release of stored energy cannot be completely excluded. Therefore, the thermomechanical consequences of a postulated instantaneous release of an extremely high amount of radiation-induced stored energy have been estimated. These estimations are based on the quasi-static solutions for line and point sources. An amplification factor has been derived from mining experience with explosives to account for the dynamic effects and the occurrence of fractures. A validation of this amplification factor has been given using postexperimental observations of two nuclear explosions in a salt formation. For some typical disposal concepts in rock salt, the extent of the fractured zone has been estimated. It appears that the radial extent of the fractured zone is limited to 5 m. Given the much larger distance between the individual boreholes and the distance between the boreholes and the boundary of the salt formation (>100 m), one can conclude that the probability of a release of radiation-induced stored energy creating a pathway for the nuclides from the containers to the groundwater is negligible.