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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.
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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Nuclear Technology
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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?
S. Cantor, W. R. Grimes
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 120-126
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16281
Articles are hosted by Taylor and Francis Online.
Through extensive testing in fission-reactor programs, molten Li2BeF4 is known to be compatible with graphite and with many useful structural metals. In service as a Controlled Thermonuclear Reactor blanket-coolant fluid, however, corrosion by this molten salt may be enhanced by (a) the effect of magnetically induced electric fields, (b) the consequences of chemical transmutations in the blanket, and (c) inadvertent mixing with other materials through leaks between fluid circuits. Fused salts flowing at high velocity across strong magnetic fields can experience intolerably large induced electromotive forces (emfs); measurements of emfs induced in aqueous solutions with electrical conductivities less than that of Li2BeF4 were found to obey Faraday’s law of electromagnetic induction even under highly turbulent flow conditions. Induced emfs, of course, are absent when the flow is parallel to the magnetic field lines and should be minimized by such flow conditions wherever possible. In regions where molten salt enters and leaves the blanket structure, induced emfs can be minimized by (a) dividing the flow among many small parallel pipes, (b) using ferromagnetic pipe sections, and (c) perhaps maintaining a frozen layer of salt on internal surfaces of pipe. Transmutations of lithium, beryllium, and fluorine in the blanket yield oxidants capable of corroding structural metals. Such corrosion can presumably be avoided by adding a reductant of suitable redox potential to the blanket. For example, low concentration of dissolved CeF3 or slurried beryllium should be capable of reacting with the oxidants and minimizing their deleterious effect. Leaks of steam or air through faulty pipes or heat exchangers would lead to markedly enhanced corrosion with most or all metals of interest, and leaks of alkali metals into Li2BeF4 would cause reduction of BeF2 to beryllium. Such inadvertent mixing would prove troublesome but of less consequence than similar leakage of steam or air into liquid alkali metals.