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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
Kalimullah, K. S. Ram, G. Srikantiah
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 376-384
Technical Note | doi.org/10.13182/NSE72-A22550
Articles are hosted by Taylor and Francis Online.
A closed form expression for the Laplace transform of lethargy-dependent neutron age τ ⊥(u) from zero lethargy to any lethargy u in a slab lattice of two materials, which are characterized by constant cross-sections, is obtained by solving Fermi age equation with a plane neutron source at the midplane of one of the slabs of an infinite lattice. Due to complexity of the Laplace transform obtained for τ⊥(u), numerical inversion is carried out to obtain (a) neutron age from 2 MeV to indium resonance energy 1.45 eV in a number of Al-H2O lattices ranging from pure aluminum to pure water and (b) neutron age as a function of lethargy in 5-5 cm AI-H2O lattice. The results obtained are in satisfactory agreement with the existing literature in those few cases in which experimental or Monte Carlo values are available. At the same Al-H2O volume ratio, neutron age is found to increase or decrease with increasing plate thickness depending on the neutron source location in aluminum or water respectively. Furthermore, everything remaining the same neutron age is smaller with the source in water than in aluminum.
