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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
J. F. Carew, A. L. Aronson, D. M. Cokinos, A. Prince, M. Todosow
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 279-285
Technical Paper | doi.org/10.13182/NSE85-A17304
Articles are hosted by Taylor and Francis Online.
A simple and accurate analytic method for calculating pressure vessel neutron damage >1-MeV fluence has been derived. The method employs asymptotic expressions for the one-speed neutron transport Green's function, together with an effective removal cross section, to propagate the neutron source from the core out to the pressure vessel. The spatial integration over the core neutron source is performed using a multipole expansion of the transport Green's function. The analytic method reproduces detailed (DOT) numerical calculations in both (r,ϴ) and (r,z) geometries to within 5%, and similar accuracy is expected in three dimensions.