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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
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Latest News
A look inside NIST’s work to optimize cancer treatment and radiation dosimetry
In an article just published by the Taking Measure blog of the National Institute of Standards and Technology, Stephen Russek—who leads the Imaging Physics Project in the Magnetic Imaging Group at NIST and codirects the MRI Biomarker Measurement Service—describes his team’s work using phantom stand-ins for human tissue.
Dave Knott, Erin Wehlage
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 331-354
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE155-331
Articles are hosted by Taylor and Francis Online.
This paper presents a description of the lattice physics code LANCER02, developed for use on boiling water reactor fuel designs at Global Nuclear Fuel and General Electric Energy, Nuclear. Included in the paper is a detailed description of the methodology used to determine the neutron flux distribution throughout the problem. The paper focuses on single-assembly analysis as well as multibundle analysis along a plane of a reactor core. A small sampling of results from the lattice physics code are compared against results generated by continuous-energy Monte Carlo analysis.
