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 Winter Conference & Expo
November 15–18, 2026
Phoenix, AZ|Arizona Grand Resort & Spa
Latest Magazine Issues
Aug 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
October 2026
Nuclear Technology
September 2026
Fusion Science and Technology
August 2026
Latest News
What’s reshaping nuclear licensing and compliance today?
Mark Reidmeyer
It is the convergence of urgency, innovation, and modernization that is reshaping nuclear licensing and compliance today.
For decades, nuclear licensing operated in a relatively stable environment built around large light water reactors, predictable review cycles, and well-established regulatory pathways. Today, that model is evolving rapidly. Advanced reactors, AI-enabled tools, digital engineering platforms, grid reliability concerns, and aggressive decarbonization goals are all pushing the industry—and regulators—to move faster and think differently.
J. R. DiStefano, K. H. Lin
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 34-45
Technical Paper | Material | doi.org/10.13182/NT73-A31316
Articles are hosted by Taylor and Francis Online.
The power density of 244Cm2O3 makes it an attractive fuel form for a variety of radioisotopic applications. To evaluate the compatibility of 244Cm2O3 with refractory metals for high-tem-perature applications, Ta, Ta - 10 wt% W, T-111, Mo, TZM, W, and W- 26 wt% Re were tested at 1650 and 1850°C, and Nb, Nb -1 wt% Zr, Ta, Ta- 10 wt% W, Mo, V, and Zr were tested at 1250°C for times up to 10 000 h. Serious reactions of 244Cm2O3 with Zr occurred at 1250°C and with Ta - 10 wt% W and T-111 at 1650°C. At both 1250 and 1650°C, the remaining materials showed good resistance to 244Cm2O3 with only limited attack, mainly in the form of shallow intergranular subsurface voids. At 1850°C, there was evidence of dissolution of tantalum and the tantalum alloys by 244Cm2O3. After 5000 and 10 000 h, tantalum had transferred from one portion of the capsule to another, and tantalum particles were found in the fuel. Less extensive mass transfer was noted with the other materials, although significant amounts of tungsten from the unalloyed tungsten and W - 26 wt% Re tests were found in the fuel.