neutronic

Neutronic is an adjective relating to neutrons and their behavior in matter. In science, neutronic analysis or neutronics studies the transport, interaction, and effects of neutrons within materials and devices. The term is most commonly used in nuclear engineering and reactor physics, where neutronic considerations determine how a system responds to neutron sources and how it can sustain or control nuclear reactions. Neutronic work contrasts with radiological, chemical, or electronic analyses that involve other particles or processes.

Key topics in neutronics include neutron transport and diffusion, scattering and absorption processes, neutron-induced fission, and neutron capture. The neutron economy, neutron energy spectrum, and the multiplication factor (k-effective) describe the balance between neutron production and loss. Moderation, absorption, and leakage affect the neutron flux and reaction rates. Materials and geometry determine cross sections and reaction probabilities, which depend on neutron energy and nuclear structure.

Computational methods are central to neutronics. The neutron transport equation, often solved with Monte Carlo or deterministic methods, yields neutron flux, reaction rates, and safety margins. Designers use neutronic calculations to optimize reactor cores, shielding, and fuel utilization, and to assess burnup, control rod worth, and subcriticality margins. Experimental measurements with neutron detectors and scattering experiments validate neutronic models and data libraries.

The term neutronic is derived from neutron and is often used as the adjective form, while neutronics is the more common noun describing the field. Neutronic concepts underpin applications in nuclear power, research reactors, material testing, and neutron-scattering science, reflecting the central role of neutrons in these areas.