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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
New work for old FLiBe? DOE considers reuse of molten salt reactor coolant
FLiBe—a mixture of lithium fluoride and beryllium fluoride—is not an off-the-shelf commodity. The Department of Energy suspects that researchers and reactor developers may have a use for the 2,000 kilograms of fluoride-based salt that once ran through the secondary coolant loop of the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory.
L. W. Nordheim
Nuclear Science and Engineering | Volume 12 | Number 4 | April 1962 | Pages 457-463
Technical Paper | doi.org/10.13182/NSE62-A26091
Articles are hosted by Taylor and Francis Online.
A new method for the calculation of resonance integrals for both homogeneous and heterogeneous assemblies has been developed and programmed for the IBM-7090. It consists in a direct numerical solution of the integral equation for the average flux in the absorber, and obviates the necessity of choosing between the narrow and wide resonance approximations. Cross sections are calculated, inclusive of Doppler broadening, interference scattering, and the E−1/2 factor in the absorption cross section. The unresolved resonances are calculated in the narrow resonance approximation under consideration of the Porter-Thomas distribution of neutron widths. Available options include (1) choice of geometry—spherical, cylindrical, slab, and homogeneous; (2) Dancoff correction for absorbers of arbitrary transparency; and (3) integral treatment of admixed scatterers. The only input data required are the resonance parameters and specifications of temperature, composition, and geometry. Everything else is handled automatically. The program calculates directly the cases of interest without requiring any additional data handling. Resonance integrals have been computed for uranium and thorium metal and UO2 and ThO2 rods of various diameters and different temperatures. Quantitative agreement with the best available measurements is reached for U238, with respect to the absolute values of the resonance integrals, as well as with respect to their temperature dependence. An interesting new result is that the intergral treatment of the oxygen in UO2 gives a noticeable correction to the resonance integral for thick absorber rods. For Th232, the agreement is not quite as perfect. The differences can, however, be traced to inconsistencies in the available cross section data.