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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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!
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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Farzad Rahnema, Dan Ilas, Shivakumar Sitaraman
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 184-194
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35324
Articles are hosted by Taylor and Francis Online.
A typical advanced boiling water reactor (BWR) pin cell configuration is used to develop numerical benchmarks for the effects of moderator and fuel properties on the eigenvalue. Results are developed for pin cell configurations with different moderator densities and temperatures and different fuel exposures and temperatures. These configurations (98) correspond to those typical of cold, hot-operating, and transient conditions in B WRs. All of the calculations were performed using the Monte Carlo code MCNP with the continuous-energy cross sections derived from version VI of the Evaluated Nuclear Data Files ENDF/B.
