ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.