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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
October 2025
Nuclear Technology
September 2025
Fusion Science and Technology
Latest News
U.K.’s NWS gets input from young people on geological disposal
Nuclear Waste Services, the radioactive waste management subsidiary of the United Kingdom’s Nuclear Decommissioning Authority, has reported on its inaugural year of the National Youth Forum on Geological Disposal forum. NWS set up the initiative, in partnership with the environmental consultancy firm ARUP and the not-for-profit organization The Young Foundation, to give young people the chance to share their views on the government’s plans to develop a geological disposal facility (GDF) for the safe, secure, and long-term disposal of radioactive waste.
S. Langer, H. R. Phillips, N. L. Baldwin
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 31-35
Technical Paper | Chemical Processing | doi.org/10.13182/NT71-A15895
Articles are hosted by Taylor and Francis Online.
An attractive recycle fuel for advanced HTGRs uses bonded fuel beds containing BISO-coated fissile and fertile particles (i.e., those having buffer and isotropic pyrolytic carbon coatings surrounding the fuel kernel). Two types of fissile material are used, 233U and 235U. The economics of the fuel cycle makes separation of these materials prior to reprocessing desirable. Laboratory-scale studies have shown that a conceptual separation process, based on the stability of (Th, U)O2 kernels in contrast to (Th, U)C2, UC2, or UO2 kernels under oxidizing conditions, is feasible on unirradiated fuel. However, damage to the oxide microspheres during irradiation is sufficient to result in fragmentation of the kernels upon removal of the pyrolytic carbon coating. Other head-end separation processes will be required to utilize bonded BISO recycle fuel in advanced HTGRs.