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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Deep Isolation validates its disposal canister for TRISO spent fuel
Nuclear waste disposal technology company Deep Isolation announced it has successfully completed Project PUCK, a government-funded initiative to demonstrate the feasibility and potential commercial readiness of its Universal Canister System (UCS) to manage TRISO spent nuclear fuel.
Seong Dae Park, Dong Won Lee, Dong Jun Kim, Seungyon Cho
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 801-806
Technical Note | doi.org/10.1080/15361055.2017.1347467
Articles are hosted by Taylor and Francis Online.
The helium cooled ceramic reflector (HCCR) test blanket module (TBM) has been designed to be installed in ITER and to verify the tritium production and the heat extraction in Korea. Lithium, beryllium, and graphite are used as a breeder, a neutron multiplier, and a reflector, respectively, which called as breeding zone (BZ) including cooling plate. The BZ was operated with the highest temperature in the TBM due to the nucler heating not only in breeding material but also structure. The margin to the allowable temperature for the breeder is very small in the current conceptual design of HCCR TBM. In the present study, feasible methods were investigated to lower the maximum temperature of the BZ. The thermal resistance and the effect of each factor were studied with a conventional CFD code, ANSYS-CFX v14.5. It is found that the thermal resistance related to the pebble beds layer was main factor to determine the breeder temperature, and the installation of the cooling fins could reduce the heat transfer resistance and lower the maximum temperature of breeder about 80°C.