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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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February 2025
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Latest News
Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
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.