Usporedite metode

	Proračun neutronskog prijenosa	Analiza sigurnosti kritičnosti
Područje	Nuklearna fizika	Nuklearna fizika
Obitelj	Process / pipeline	Process / pipeline
Godina nastanka	1942	1938
Tvorac	Enrico Fermi, Leslie Szilard	Otto Hahn, Fritz Strassmann
Vrsta	computational simulation pipeline	safety assessment methodology
Temeljni izvor	Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons.	American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40.
Drugi nazivi	neutron diffusion, neutron migration, transport equation solution	nuclear safety assessment, chain reaction analysis, fissile material control
Srodne	5	5
Sažetak	Neutron transport calculation is a computational method for determining the distribution and behavior of neutrons in a nuclear medium, developed during the Manhattan Project in the 1940s. It solves the Boltzmann transport equation to predict neutron flux, energy spectra, and reaction rates essential for reactor design and shielding analysis.	Criticality safety analysis is a systematic evaluation of fissile material systems to ensure nuclear chain reactions remain controlled, originating from Hahn and Strassmann's 1938 discovery of nuclear fission. It determines safe limits on fissile mass, concentration, geometry, and spacing using neutron transport calculations and experimental validation to prevent uncontrolled nuclear excursions in storage, processing, and transportation.