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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
April 2025
Latest News
Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
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.