Сравнение методов

	Кинетика реактора	Анализ безопасности критичности
Область	Ядерная физика	Ядерная физика
Семейство	Process / pipeline	Process / pipeline
Год появления	1942	1938
Автор метода	Enrico Fermi, George Westinghouse	Otto Hahn, Fritz Strassmann
Тип	dynamic systems analysis	safety assessment methodology
Основополагающий источник	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.
Другие названия	neutron kinetics, power transient modeling, reactor control analysis	nuclear safety assessment, chain reaction analysis, fissile material control
Связанные	5	5
Сводка	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.