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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
S. I. Bhuiyan, R. W. Roussin, J. L. Lucius, J. H. Marable, D. E. Bartine
Nuclear Science and Engineering | Volume 93 | Number 3 | July 1986 | Pages 313-317
Technical Note | doi.org/10.13182/NSE86-A17760
Articles are hosted by Taylor and Francis Online.
Three models, a linear, exponential or BEST, and a power model, developed using sensitivity theory to predict deep-penetration neutron transport in practical shielding problems, have been generalized into a common expression. One can obtain any of the above three models from this generalized expression simply by choosing the proper index parameters. Subsequently, a scheme for implementation of this into a computer code was adopted in “SENATOR.” SENATOR replaces the SENTINEL module of the Oak Ridge National Laboratory (ORNL) FORSS system. The supporting data bases (i.e., the sensitivity profile) and the Fortran code, along with some utility programs, are assembled in a package identified as CONSENT and can be obtained through the Radiation Shielding Information Center at ORNL.