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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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. Goldfarb, W. Ponton
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1265-1268
Impurity Control and Vacuum Technology | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A39941
Articles are hosted by Taylor and Francis Online.
A system was designed and installed on the Tokamak Fusion Test Reactor (TFTR) to monitor temperatures and to control electrical heaters for 150 °C bakeout. This system, an adjunct to the hot air vacuum vessel heating system, is used for heating vacuum vessel port covers, neutral beam ducts, and diagnostic vacuum enclosures contiguous with the main vacuum vessel. The control scheme is based on an Allen-Bradley 2–30 Programmable Controller (PC) which acquires thermocouple data, calculates temperature differentials and provides proportional control of the heater power supplies. Temperature differentials between the vessel walls heated by hot air and the electrically heated portions are limited by the system to avoid excessive thermal stress as the machine temperature is raised expeditiously to bakeout level. The system prints out operating parameters and operates independent of the main TFTR control computer which is interconnected only for data display and archiving.