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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
April 2024
Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
Remembering Joseph M. Hendrie
Joseph M. Hendrie
To those of us who knew Joe, even prior to his appointment as chair of the Nuclear Regulatory Commission, it is an understatement to say that he was a larger-than-life member of the nuclear science and technology enterprise. He was best known to the broader community for two major accomplishments: the design and construction of the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory and the creation of the standard review plan (SRP) for the U.S. Atomic Energy Commission.
In addition to the products of these endeavors becoming major fundaments to their respective communities, they were uniquely Joe. The safety analysis report for the HFBR was written essentially single-handedly by him. This was true of the SRP as well, which became the key safety review document for the NRC as it performed safety reviews for the growing number of power reactor applications in the United States. His deep technical knowledge of nuclear engineering and his extraordinary management skills made this possible.
Sebahattin Ünalan, S. Orhan Akansu
Fusion Science and Technology | Volume 34 | Number 2 | September 1998 | Pages 109-127
Technical Paper | doi.org/10.13182/FST98-A57
Articles are hosted by Taylor and Francis Online.
Effects on the neutronic performance of the hybrid blanket rejuvenating light water reactor and CANDU spent fuels of moderators (Be, C, and D2O) inserted between the fusion chamber and the fissile zone of deuterium-deuterium and deuterium-tritium-driven hybrid reactor were investigated to obtain the best rejuvenation performance and more energy production. The calculations were carried out for different thicknesses of the moderator zone (DR). In addition, to eliminate local heating, the analysis was also repeated for reduced radius of the spent fuel rods in the first and the second fuel rows of the fissile zone.It was observed that while Be and D2O improved the rejuvenation performance and energy production, C had a negligible effect. All moderators decreased the tritium breeding capability of the hybrid reactor with increasing DR values. To breed enough tritium (tritium breeding ratio: >1.05), the moderator zone thickness was determined to be smaller than DR = 6 cm as an average value. The rejuvenation performance reached a maximal value of DR = ~4 cm, increased two times in comparison with the blanket without moderator material, although the energy production was almost constant. However, to produce more energy, DR has to be ~20 cm. The energy releasing in the hybrid blanket with DR [approximately equal to] 20 cm is nearly two times that in the hybrid blanket without moderator material. The high energy production caused the fuel rod temperatures in the first fuel row of the fissile zone to reach the melting point. Hence, as a positive result, radiation damage in the first wall did not vary. However, the melting problem was eliminated by reducing the radius of the fuel rods in the first and second fuel rows, and the neutronic performance of the hybrid reactor has not been affected by this radius reduction.