विधियों की तुलना करें

	क्रिटिकैलिटी सुरक्षा विश्लेषण	विकिरण खुराक मूल्यांकन
क्षेत्र	नाभिकीय भौतिकी	नाभिकीय भौतिकी
परिवार	Process / pipeline	Process / pipeline
उद्भव वर्ष	1938	1928
प्रवर्तक	Otto Hahn, Fritz Strassmann	International Commission on Radiological Protection (ICRP)
प्रकार	safety assessment methodology	computational health assessment pipeline
मौलिक स्रोत	American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40.	International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4).
उपनाम	nuclear safety assessment, chain reaction analysis, fissile material control	dose calculation, exposure assessment, radiation hazard evaluation
संबंधित	5	5
सारांश	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.	Radiation dose assessment is a systematic evaluation of human exposure to ionizing radiation from external or internal sources, formalized by the International Commission on Radiological Protection (ICRP) in the late 20th century. It combines radiation transport calculations with biological effect models to quantify absorbed dose, equivalent dose, and effective dose for worker safety and public health protection.