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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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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.
A. C. Hoyle, G. R. Howey
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 25-32
Technical Paper | doi.org/10.13182/NT65-A20460
Articles are hosted by Taylor and Francis Online.
Two innovations in the design of the NPD primary system were to use carbon steel for piping and to fill and test with heavy water only. Resulting savings were $400 000 and $100 000, respectively. Specifications ensured satisfactory surface and fluid states following commissioning. Operation of the carbon steel system has been very satisfactory except for a fueling-machine failure when foreign materials were introduced into the system. The pD of the system has been maintained between 10 – 11, the dissolved O2 concentration at < 0.01 parts/106 and the crud level during steady-state operation at < 0.01 parts/106 with peak crud concentrations of < 0.1 parts/106. During pressure testing, 496 lbs of reactor grade D2O were lost at a cost of $12 400 at today's prices; nevertheless this loss is acceptably low. Significantly, the corrosion rate, the radiolytic damage, and the gas formation were never as great as had been expected. Carbon steel is therefore recommended for other pressurized water systems. The experience gained in operating NPD for two years showed the economic feasibility of pressurized D2O as a reactor coolant and pointed out the improvements required. Consequently, the target figure of 10 lb/day loss of D2O for a 200-MWe reactor now appears feasible.