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
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
K. Birch, M. Mielcarek (NWMO)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 164-172
The NWMO has developed a concept for containment and isolation of CANDU used fuel bundles in a Deep Geological Repository. The design is similar for emplacement in either a crystalline or sedimentary rock geosphere. The design consists of a 2.51 m long, 0.56 m diameter hemi-head metallic used fuel container (UFC), placed in a bentonite over-pack referred to as a Buffer Box. The Buffer Boxes are placed transversely in a stacked configuration in a drill and blast excavated placement room, and are separated by bentonite Spacer Blocks to limit the maximum temperature to 100° C at the UFC surface.
A critical component of this concept is the buffer, which consists of 100% Wyoming bentonite fabricated into two products:
(i) Highly Compacted Bentonite (HCB) (minimum dry density 1.7 g/cm3); and
(ii) Gap Fill Material (GFM) (a well graded granular material with a maximum particle size of 8 mm, with ? 10 % by mass particle size of less than 75 ?m, and with a minimum as-placed dry density of 1.41 g/cm3).
Similar bentonite materials are used as a buffer by several international nuclear waste management organizations in their repository designs. However, the placement concept is unique to the NWMO and the production and placement of the buffer needs to be demonstrated to build confidence in the design.
The objectives of this program were to fabricate full scale HCB blocks and to conduct a full scale GFM placement demonstration. The HCB block concept has progressed from the fabrication of 0.3 m by 0.1 m by 0.1 m bricks to the cold isostatic pressing of the full scale 3 m by 1 m by 0.5 m blocks. Test programs have confirmed the uniformity of the dry density (? 1.75 g/cm3) and moisture content (? 20 %) of the blocks, and have shown that the HCB blocks can be pressed to predicted densities that are consistent with small scale trials.
The GFM placement program has progressed from placing Gap Fill like material (crushed limestone with a similar particle size distribution), using commercially available agricultural augers in a 1 m by 1 m by 0.15 m test frame, to placing MX-80 bentonite GFM in a full scale, smooth wall representative gap using a purpose built screw conveyor. The full scale GFM demonstrations achieved dry densities of between 1.5 to 1.59 g/cm3. The GFM placement demonstration along with the full scale block pressing program demonstrated that the minimum required dry density for the two buffer components can be consistently exceeded.