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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
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
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
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.
Magdi Ragheb, George H. Miley
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2061-2066
Fusion Reactor | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24588
Articles are hosted by Taylor and Francis Online.
The LOTRIT inertial confinement reactor concept employs a deuterium burning target with a DT spark trigger core. This eliminates the need for tritium breeding in a blanket, and leads to a minimization of the tritium inventory and of the possibility of metal fire hazards if lead is used instead of lithium for first wall protection. The active fuel inventory in the fuel cycle and blanket per MJ of energy produced is only 5 percent of the DT case. The most significant reduction in the total tritium inventory is in the target manufacture and storage areas, and is about 1.8% of the DT case per unit of fusion energy produced. If the goal is to reduce the risk from tritium releases from fusion reactors to below that of fission reactors, it is estimated that the tritium releases must be maintained at 0.13–5.0 Ci/day. Attaining these values will be costly, technologically difficult and will constrain the design options in DT-based systems, but may be within the realm of systems using the LOTRIT concept.