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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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.
S.K. Erents
Fusion Science and Technology | Volume 6 | Number 2 | September 1984 | Pages 453-458
Technical Paper | Selected papers from the Ninth International Vacuum Congress and the Fifth International Conference on Solid Surfaces (Madrid, Spain, September 26-October 1, 1983) | doi.org/10.13182/FST84-A23221
Articles are hosted by Taylor and Francis Online.
Plasmas produced while using the MkII Bundle Divertor on DITE have been studied using a combined Langmuir/heat flux probe technique. Ion saturation currents and deposited powers to bolometers facing both the ion and electron drift directions have been measured. A substantial depression of the ion flux on the ion side is recorded, which has been explained by the shorter connection length to the divertor target plate. Radial profiles of electron temperature Te, ion temperature Ti, and local plasma density, ne have been calculated from the measurements. These are time resolved and have been studied both before and during neutral beam injection. E-folding lengths for deposited power of ∼ 1.0cm have been measured, but those for ion and electron temperature are much longer. Calculated values of Ti range from 50 to a few hundred eV, those for Te are an order of magnitude lower. An estimate of carbon limiter sputtering has been made which suggests that for the present discharge conditions (plasma current 150 kA, central density 1.5 – 3 × 1019 m−3), the sputtering rises with increasing density during neutral injection, although a fall in Ti is calculated.