neutron cross section


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neutron cross section

[′nü‚trän ′krȯs ‚sek·shən]
(nuclear physics)
A measure of the probability that an interaction of a given kind will take place between a nucleus and an incident neutron; it is an area such that the number of interactions which occur in a sample exposed to a beam of neutrons is equal to the product of the number of nuclei in the sample and the number of neutrons in the beam that would pass through this area if their velocities were perpendicular to it.
McGraw-Hill Dictionary of Scientific & Technical Terms, 6E, Copyright © 2003 by The McGraw-Hill Companies, Inc.
References in periodicals archive ?
The number of tested elements was limited to 57 since in many cases the neutron cross section data were unavailable in JEFF-3.1 library.
However, the small fast neutron cross section with carbon resulted in a minute contribution to the overall observed response [41].
The accuracy of the neutron flux a key factor for the measurement of the neutron cross section with a reasonably small error.
The revised Declassification Guide also permits the publication of the thermal neutron cross section of xenon-135.
Experiment planning tools in DAVE Neutron Cross Section Table (Fig, 2) Calculator (Sect.
Topics include power reactor surveillance, including justifications for extended service life in Russian reactors,; test reactors, accelerators, and advanced systems, including determination of adjusted neutron spectra and characterization of neutron fields using innovative techniques; nearly a dozen papers on benchmarks and inter-comparisons, including verification of helium generation,; cross sections and nuclear data in damage correlations, including an international evaluation of the neutron cross section standards; transport calculations; adjustment methods, including those for upgrades and to produce more reliable predictions; and an array of experimental techniques.
The uncertainties considered are those resulting from uncertainties in input data variable, such as neutron cross section data, manufacturing uncertainties in material compositions, and geometrical dimensions.
will be the flux absorbed in the reaction cell where [sigma] is the neutron cross section, N the density of helium atoms in the chamber and Idead and d are the lengths of the dead space and the diameter of the reaction chamber (25 mm) respectively.
The ENDF/B-VI Neutron Cross Section Measurement Standards, NISTIR 5177 (1993).
It would allow precise measurements of important neutron cross section standards at near-thermal energies, such as [.sup.6]Li, [.sup.10]B, and [.sup.235]U.
The effective thermal neutron cross section [sigma] measured with unpolarized neutrons is a statistical sum of the singlet [[sigma].sub.s] and triplet [[sigma].sub.t] cross sections