Neutron moderator

Science with neutrons
Foundations
Neutron temperature Flux, Radiation, Transport Cross section, Absorption, Activation
Neutron scattering
Neutron diffraction Small-angle neutron scattering GISANS Reflectometry Inelastic neutron scattering Triple-axis spectrometer Time-of-flight spectrometer Backscattering spectrometer Spin-echo spectrometer
Other applications
Neutron tomography Activation analysis, Prompt gamma activation analysis Fundamental research with neutrons: Ultracold neutrons, Interferometry Fast neutron therapy Neutron capture therapy
Infrastructure
Neutron sources: Research reactor, Spallation, Neutron moderator Neutron optics: Reflector, Supermirror Detection
Neutron facilities
America: HFIR, LANSCE, NIST CNR -SNS Oceania: OPAL Asia: J-PARC, HANARO Europe: BER II, FRM II, ILL, ISIS Neutron and Muon Source, JINR, SINQ Historic: IPNS, HFBR Under construction: ESS
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In nuclear engineering, a neutron moderator is a medium that reduces the speed of fast neutrons, ideally without capturing any, leaving them as thermal neutrons with only minimal (thermal) kinetic energy. These thermal neutrons are immensely more susceptible than fast neutrons to propagate a nuclear chain reaction of uranium-235 or other fissile isotope by colliding with their atomic nucleus.

Water (sometimes called "light water" in this context) is the most commonly used moderator (roughly 75% of the world's reactors). Solid graphite (20% of reactors) and heavy water (5% of reactors) are the main alternatives.^[1] Beryllium has also been used in some experimental types, and hydrocarbons have been suggested as another possibility.