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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
William R. Mills, Jr., L. Scott Allen, Richard L. Caldwell, George N. Salaita, Tom J. Gray
Nuclear Science and Engineering | Volume 21 | Number 3 | March 1965 | Pages 346-356
Technical Paper | doi.org/10.13182/NSE65-A20038
Articles are hosted by Taylor and Francis Online.
Pulsed-neutron experiments have been performed in a borehole model to determine the effects of tool position, borehole fluid, and source-detector spacing on pulsed-neutron/thermal-neutron logging. Neutron-time distributions were measured with various combinations of the above parameters in a sand model of 32.5% porosity filled with fresh water or salt water with 230 g/liter NaCl. Neutron lifetimes determined from the distributions indicate the degree of validity of the assertion that undesirable borehole effects are largely eliminated by this logging method. A numerical computer code (CUNLAP) has been developed to solve the time-dependent, three-group diffusion equations which apply to borehole geometry. Results of test calculations are presented and compared to the experiments in a semiquantitative way. The numerical results are also compared to those of an analytical, fundamental-mode calculation. It is shown that the latter approach is inappropriate for the type of measurement and size of system used in experiments of this nature.