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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
S. Domingo, Y. Herreras, F. Sordo, A. Lafuente, J. M. Perlado
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 710-717
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8992
Articles are hosted by Taylor and Francis Online.
This paper presents a methodology for 3D neutronic calculations suitable for complex and extensive geometries. The geometry of the system design is first fully modeled with a CAD program; this modeling is then processed - requiring few simplifications - with MCNP-CAD interface in order to generate a MCNP geometry file. Neutronic irradiation results are finally achieved running the MCNP program, where the geometry input card used is directly the MCNP-CAD interface output. This methodology enables accurate neutronic calculations for complex geometries characterized by high detail levels, such as ITER or other fusion facilities (IFMIF), in which we are presently involved.This procedure has been applied to the Fast Ignition Fusion Reactor KOYO-F. We have determined the neutron fluxes and energy deposition in the reactor blanket, and obtained the front panel damage and activation for several alternative front panel materials. To carry out this calculation, KOYO-F blanket design is modeled using CATIA V5, and the selected CAD-MCNP interface is MCAM, developed by the FDS Team (China). The activation of the front panel material is finally evaluated with our code ACAB, based on the neutronic irradiation results provided by MCNP.