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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.
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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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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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Fusion Science and Technology
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.
R Haange, P Ballantyne, A C Bell, S J Booth, C Caldwell-Nichols, P Chuilon, J L Hemmerich, J-F Jaeger, A Konstantellos, R Lässer, G Newbert, D Wong, MEP Wykes
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 253-255
Design, Operation, and Maintenance | doi.org/10.13182/FST92-A29753
Articles are hosted by Taylor and Francis Online.
The present schedule of JET includes an experimental campaign with D-T plasmas at the end of the Project programme. A dedicated facility, the Active Gas Handling System (AGHS), has been designed and is being commissioned to process the torus exhaust streams and to recycle tritium and deuterium. The AGHS is expected to process a maximum throughput of 30g tritium daily and total tritium inventory will not exceed 90g. The design is subject to a comprehensive safety analysis which must show that stringent safety criteria are met. In parallel to the AGHS installation, the JET torus and its auxiliary systems are being analysed for compliance with the same safety criteria. Modifications are being implemented where required. The AGHS installation is nearing completion and non-tritium commissioning is underway. The JET D-T phase will be preceded by a very short campaign of a few D-T pulses which can be conducted with a very small inventory of tritium, thus allowing this to be undertaken at an early stage in order to obtain important data prior to the start of the full D-T phase. JET will be the first experimental facility where the tritium fusion fuel processing cycle will be closed (albeit without breeding) and hence important experience and experimental data are expected to be gained for the next generation of fusion devices.