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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
Pierre Benoist
Nuclear Science and Engineering | Volume 86 | Number 1 | January 1984 | Pages 22-40
Technical Paper | doi.org/10.13182/NSE84-A17967
Articles are hosted by Taylor and Francis Online.
A simple formalism, which can be introduced into routine analyses, is presented for the calculation of the effect of sodium voiding on neutron leakages in a fast reactor lattice. The diffusion coefficients in plane or in two-dimensional lattices are calculated following a method that is very analogous to the method proposed earlier by the author for the treatment of thermal reactors. The two situations, sodium present and sodium voided, are calculated with the same approximations. It is known that it is impossible in the situation where the sodium is voided to calculate buckling-independent diffusion coefficients, for they diverge. These coefficients are hence calculated in both situations at the lowest order of the expansion in terms of the buckling, which introduces a logarithmic term. The calculation is performed in the actual geometry of the lattice without cylindricalizing the cell.