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Division Spotlight
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?
S. G. Druce, B. C. Edwards
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 487-498
Technical Paper | Materials | doi.org/10.13182/NT55-487
Articles are hosted by Taylor and Francis Online.
The manganese-molybdenum-nickel steels ASTM A533B and A508 are extensively used in the fabrication of reactor pressure vessels and steam generators in light water reactors. These components receive heat treatments during fabrication and in operational service that could lead to a possible degradation of toughness as a result of grain boundary segregation of alloying and impurity elements promoting temper embrittlement. The susceptibilities to temper embrittlement of commercially produced thick section A533B Class 1 and A508 Class 3 steels have been investigated by Charpy impact testing following isothermal heat treatments in the 300 to 600°C temperature range for periods up to 5000 h. In addition, the combined effects of austenite grain size and impurity content have been studied using experimental melts of the 533B/508 Class 3 type alloy composition doped with specific impurities. The lower and upper shelf fracture modes were examined as a function of aging treatment, and samples exhibiting a low temperature intergranular fracture mode were examined using Auger Electron Spectroscopy to determine the amount and types of elements segregated at the grain boundaries. While the commercial materials have been found to exhibit only small increases in the ductile-brittle transition temperature after isothermal aging at 450 to 500°C, large increases are observed for the experimental material with a high phosphorus content. The degree of embrittlement is strongly dependent on austenite grain size, increasing with increasing grain size. These results indicate the need for close control of chemical composition of the steel in inhibiting embrittlement and cracking in the weld coarse-grained, heat-affected zone regions.