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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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?
L. F. Parsly
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 472-485
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16259
Articles are hosted by Taylor and Francis Online.
The spray program conducted at the Nuclear Safety Pilot Plant in 1967–1970 is summarized. Sprays have been proposed as a means for removing fission products from reactor containment building atmospheres following a loss-of-coolant accident. The problem was dealt with in three parts: removal of elemental iodine, removal of organic iodides, and removal of particles. Thirty iodine removal experiments were performed using borax, borax plus thiosulfate, and boric acid. Both borax and borax-thiosulfate were highly effective in removing elemental iodine. Boric acid is much more effective than expected. Fifteen methyl iodide removal experiments were performed. Only borax-thiosulfate at elevated temperatures removed methyl iodide at a significant rate. Extrapolation of the data to a large PWR indicates the dose reduction factor would be 1.1 for the flow, drop size, and reagent concentration normally specified. This can be improved by increasing flow and/or concentration or by reducing drop size. Fifteen particle removal experiments have been done. These show that phenomena associated with steam condensation make the major contribution to removing particles. The results indicate that sprays will remove particles effectively.