Definition of Neutron flux

1. Noun. The rate of flow of neutrons; the number of neutrons passing through a unit area in unit time.

Generic synonyms: Flux

Definition of Neutron flux

1. Noun. (physics) The number of neutrons passing through one square centimeter of a given target in one second. ¹

¹ Source: wiktionary.com

Lexicographical Neighbors of Neutron Flux

neutrinospheric
neutro-
neutroclusion
neutrois
neutron
neutron-rich
neutron-richer
neutron-richest
neutron-star
neutron activation analysis
neutron bomb
neutron bombs
neutron capture therapy
neutron diffraction
neutron drip line
neutron flux
neutron fluxes
neutron interferometer
neutron number
neutron numbers
neutron optics
neutron radiation
neutron scattering
neutron spectrometry
neutron star
neutron stars
neutronic
neutronium
neutronization
neutrons

Literary usage of Neutron flux

Below you will find example usage of this term as found in modern and/or classical literature:

1. Beneficial Uses and Production of Isotopes: 2000 Update by Nea, OECD Nuclear Energy Agency (2000)
"neutron flux is a key parameter for the isotope production capabilities of reactors. Practically all the research reactors producing isotopes have a thermal ..."

2. Proceedings of the Sixth Meeting of the Task Force on Shielding Aspects of by OECD Nuclear Energy Agency (2004)
"Because of the inelastic scattering of high-energy neutrons in the iron layer the low-energy neutron flux spectrum (particularly below a few hundred keV) ..."

3. Basic Studies in the Field of High-Temperature Engineering: Second by Nea, OECD Nuclear Energy Agency, Nihon Genshiryoku Kenkyūjo (2002)
"It can be seen that substantial neutron flux exists even in an out-of-core region. A length of the rig was enlarged as long as possible and the ..."

4. Utilisation and Reliability of High Power Proton Accelerators: Workshop by NEA Nuclear Science Committee (2003)
"neutron flux therefore is a better predictor than the gamma flux, "accounting" for 15% out of the 38% discrepancy (Table 3). The fourth described radiation ..."

5. Fission Gas Behaviour in Water Reactor Fuels: Seminar Proceedings, Cadarache by OECD Nuclear Energy Agency (2002)
"For the sake of completeness it is worth mentioning other possible effects such as grain size, fast neutron flux, fuel densification and fuel relocation. ..."

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