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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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?
G. W. Keilholtz, R. E. Moore, M. F. Osborne
Nuclear Technology | Volume 4 | Number 5 | May 1968 | Pages 330-336
Technical Paper and Note | doi.org/10.13182/NT68-A26398
Articles are hosted by Taylor and Francis Online.
Solid cylindrical specimens (½- × ½-in.) of the monocarbides of Ti, Zr, Ta, Nb, and W, made by 1) hot pressing, 2) slip casting and sintering, and 3) explosion-pressing and sintering, were irradiated at 300 to 700°C. Fast-neutron (> 1 MeV) exposures ranged from 0.8 to 5.4 × 1021 n/cm2 in a fast-neutron flux profile which ranged from 0.6 to 2.6 × 1014 n/(cm2 sec). The order of decreasing fracture of specimens made by 1) and 2) was Ta, Zr, Nb, Ti, and W. Specimens made by 3) not only fractured at lower neutron doses than those made by 1) and 2), but there was also less difference in gross damage among the five carbides. Tungsten carbide expanded in volume by ∼0.6% and the other carbides by 2 to 3% upon exposure to fast doses of 1 to 2 × 1021 n/cm2. Higher doses produced either a decrease in volume toward the initial volume or no further change. Volume changes represented crystal volume changes since there was no grain boundary separation. Less than 50% of the crystal expansion was accounted for by increases in lattice parameters. The major cause of damage to carbides is postulated to result from point defects produced by fast neutrons. It is suggested that most of the initial volume expansion is caused by the formation of defect agglomerates too large to affect measured values of the lattice parameters. Slow neutrons of the irradiation spectrum may have contributed to premature fracturing of explosion-pressed specimens through absorptions by added Co and Ni binder at the grain boundaries.