So sánh phương pháp

	Động lực học Lò phản ứng	Phân tích An toàn S tới hạn
Lĩnh vực	Vật lý hạt nhân	Vật lý hạt nhân
Họ	Process / pipeline	Process / pipeline
Năm ra đời	1942	1938
Người khởi xướng	Enrico Fermi, George Westinghouse	Otto Hahn, Fritz Strassmann
Loại	dynamic systems analysis	safety assessment methodology
Công trình gốc	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.
Tên gọi khác	neutron kinetics, power transient modeling, reactor control analysis	nuclear safety assessment, chain reaction analysis, fissile material control
Liên quan	5	5
Tóm tắt	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.