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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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?
H. E. Zittel, T. H. Row
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 436-443
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16253
Articles are hosted by Taylor and Francis Online.
It has been proposed that, following a pressurized water reactor (PWR) loss-of-coolant accident (LOCA), sprays be used for the twofold purpose of pressure suppression and fission product (largely 131I) removal. These proposed sprays must operate under severe conditions of high energy radiation (∼3 × 108 rads) and temperature (∼135°C). Studies have been carried out on a series of such sprays to ascertain their stability under these conditions. It was found that several of the solutions exhibit satisfactory behavior under accident conditions while others were discarded from consideration because of either thermal and/or radiation instability. The two sprays found to demonstrate acceptable stabilities under test conditions are the basic borate (0.15N NaOH-3000 ppm B) and basic borate thiosulfate (1 wt% Na2S2 O3-0.15N NaOH-3000 ppm B). However, even these demonstrate a radiolytic gas generation (H2) sufficient to be a possible safety hazard. Various studies have been carried out to establish G(H2) values and/or equilibrium radiolytic gas concentrations. Other studies were carried out on possible spray solution interaction with reactor containment metals and alloys.