مقایسهٔ روش‌ها

	سینتیک راکتور	تحلیل ایمنی بحرانایی
حوزه	فیزیک هسته‌ای	فیزیک هسته‌ای
خانواده	Process / pipeline	Process / pipeline
سال پیدایش	1942	1938
پدیدآور	Enrico Fermi, George Westinghouse	Otto Hahn, Fritz Strassmann
نوع	dynamic systems analysis	safety assessment methodology
منبع بنیادین	Lamarsh, J. R. (1983). Introduction to Nuclear Engineering (2nd ed.). Addison-Wesley.	American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40.
نام‌های دیگر	neutron kinetics, power transient modeling, reactor control analysis	nuclear safety assessment, chain reaction analysis, fissile material control
مرتبط	5	5
خلاصه	Reactor kinetics is the study of neutron population dynamics in a reactor core, originating from Fermi's first controlled chain reaction in 1942. It models power changes in response to control rod movements, temperature feedback, and accidental transients using coupled differential equations accounting for prompt and delayed neutrons, to ensure safe operation, predict transient behavior, and design control systems.	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.