Neutron flux
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The neutron flux is a scalar quantity used in nuclear physics and nuclear reactor physics. It is the total distance travelled by all free neutrons per unit time and volume.[1] Equivalently, it can be defined as the number of neutrons travelling through a small sphere of radius in a time interval, divided by a maximal cross section of the sphere (the
The neutron fluence is defined as the neutron flux integrated over a certain time period. So its dimension is and its usual unit is cm−2 (reciprocal square centimetre). An older term used instead of cm−2 was "n.v.t." (neutrons, velocity, time).[3]
Natural neutron flux
Neutron flux in
Earth atmospheric neutron flux, apparently from thunderstorms, can reach levels of 3·10−2 to 9·10+1 cm−2 s−1.[5][6] However, recent results[7] (considered invalid by the original investigators[8]) obtained with unshielded scintillation neutron detectors show a decrease in the neutron flux during thunderstorms. Recent research appears to support lightning generating 1013–1015 neutrons per discharge via photonuclear processes.[9]
Artificial neutron flux
Artificial neutron flux refers to neutron flux which is man-made, either as byproducts from weapons or nuclear energy production or for a specific application such as from a
Within a nuclear fission reactor, the neutron flux is the primary quantity measured to control the reaction inside. The flux shape is the term applied to the density or relative strength of the flux as it moves around the reactor. Typically the strongest neutron flux occurs in the middle of the reactor core, becoming lower toward the edges. The higher the neutron flux the greater the chance of a nuclear reaction occurring as there are more neutrons going through an area per unit time.
Reactor vessel wall neutron fluence
A
See also
References
- OL 3512075M.
- OL 27986790M – via Internet Archive.
- ^ M. F. Kaplan (August 1983). Nuclear Radiation and the Properties of Concrete (PDF). University of Cape Town. p. 2. Retrieved 14 September 2022.
- .
- PMID 22540588.
- .
- PMID 25860750.
- PMID 26551144.
- PMID 28357174.
- ^ Nuclear Power Plant Borssele Reactor Pressure Vessel Safety Assessment, p. 29, 5.6 Neutron Fluence Calculation.