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
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Edwin M. Larsen, S. I. Abdel-Khalik, Mark S. Ortman
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 12-26
Technical Paper | Reactor | doi.org/10.13182/NT78-A32129
Articles are hosted by Taylor and Francis Online.
The 1000-MW(electric) laser fusion reactor design of the University of Wisconsin, SOLASE, is fueled by inserting cryogenic deuterium-tritium pellets containing a milligram of fuel into a spherical cavity having a 6-m radius at a rate of 20 Hz. The cavity is surrounded by a honeycomb graphite structure divided into 16 longitudinal segments through which lithium oxide particles (100 to 200 µm in diameter and with a pore length of 1 µm) flow by gravity. The total oxide inventory is 1 mg. The lithium oxide, which contains 0.1 wt% water, serves as both a tritium breeder and a heat transport medium. The oxide enters the blanket at 673 K and exits at 873 K except for a 2% side stream exiting at 1123 K, from which the tritium is recovered. At this temperature, a residence time of 300 s at a flow rate of 163 kg/s is required to condense the daily tritium supply as HTO on a cold surface. The 873 K lithium oxide is transported to a steam generator fabricated from Croloy tubes. In addition to the fuel, the container, either borosilicate glass or polyvinylalcohol (PVA), and a polymer ablator, the pellets contain a high-Z material, here xenon. Also, ∼30 mg of neon are frozen on the outside surface to ensure cryogenic conditions during flight. Some pellet constituents will react with the wall, resulting in erosion. Unburned hydrogen species will react with graphite to form acetylene at a rate estimated to be 63 pm/s (2 mm/yr) for glass and PVA shells at pumping speeds of 6.4 and 8.4 Pa · m3/s (4.8 × 104 and 6.3 × 104 Torr · ℓ/s) at 300 K, respectively. The oxygen debris will erode the graphite by carbon monoxide formation at maximum rates of 6.3 and 25.4 pm/s, respectively, for glass and PVA shells. The total erosion rate is within the expected lifetime of the blanket (1 yr) based on radiation damage studies. The reactor exhaust is predominantly neon, so that hydrogen isotope recovery and recycle is essentially a neon purification process. The fill time for glass pellets is estimated to be 5 days and for PVA pellets, 1 day. This results in a total tritium inventory of 26 and 11 kg, respectively, for a lithium oxide blanket containing 1 kg of tritium. Anticipated tritium losses include 1.5 to 2.2 kBq/kg H2O (40 to 60 nCi/ℓ H2O) of tritium to the water in the reheaters and steam generators and <400 kBq/s (1 Ci/day) for atmospheric losses. This study shows the necessity for experimental work on the thermodynamic properties of well-characterized lithium oxide.