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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
Latest News
Oak Ridge focuses neutron scattering studies on TRISO fuels
Oak Ridge National Laboratory is reporting a development in TRISO fuel research that could help evaluate high-temperature gas reactor fuels. ORNL researchers used the Spallation Neutrons and Pressure Diffractometer at the lab’s Spallation Neutron Source to make neutron scattering measurements on TRISO fuel particles containing high-assay low-enriched uranium (HALEU).
B. P. Bromley, A. V. Colton
Nuclear Technology | Volume 207 | Number 8 | August 2021 | Pages 1193-1215
Technical Paper | doi.org/10.1080/00295450.2020.1853466
Articles are hosted by Taylor and Francis Online.
Lattice physics and core physics studies have been carried out to investigate the reactor physics feasibility of destroying americium (Am) and curium (Cm) using special target fuel bundles in blanket fuel channels in a heterogeneous seed-blanket pressure tube heavy water reactor (PT-HWR) core fueled primarily with natural uranium. Results indicate that it should be feasible to achieve net-zero production of Am in a single PT-HWR core using 10 to 16 dedicated blanket channels containing Am-based target bundles while only one dedicated blanket channel would be required for achieving net-zero production of Cm. While the use of target blanket fuel bundles with fuel elements made of Am or Cm mixed with thorium (Th) in oxide form ((Am,Th)O2, (Cm,Th)O2) is expected to be suitable for transmutation purposes, the use of fuel elements made of pure americium oxide, especially those in the form of AmO1.55, may not be suitable for transmutation purposes because of potential issues with fuel melting under high-power operations or postulated accident scenarios. The potential to achieve net-zero production of Am and Cm in a single thermal-spectrum reactor, such as a PT-HWR, could help eliminate the need to build and qualify a deep geological repository (DGR) capable of storing minor actinides for a long time (>1 million years). At the very least, the size and/or number of DGRs required for storing radioactive waste could be reduced significantly. Thus, destroying Am and Cm in PT-HWRs could be regarded as a viable solution to the perceived problem of nuclear waste and may help improve public acceptance of the use of nuclear energy. In addition, it may be possible to apply a similar approach for destroying MAs in other Generation III+ (Gen-III+)/Generation IV (Gen-IV)/small modular reactor (SMR) technologies.