Comparar métodos
Revisa los métodos seleccionados uno junto a otro; las filas que difieren aparecen resaltadas.
| Análisis de Seguridad de Criticidad× | Evaluación de la Dosis de Radiación× | |
|---|---|---|
| Campo | Física nuclear | Física nuclear |
| Familia | Process / pipeline | Process / pipeline |
| Año de origen≠ | 1938 | 1928 |
| Autor original≠ | Otto Hahn, Fritz Strassmann | International Commission on Radiological Protection (ICRP) |
| Tipo≠ | safety assessment methodology | computational health assessment pipeline |
| Fuente seminal≠ | American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40. link ↗ | International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4). link ↗ |
| Alias | nuclear safety assessment, chain reaction analysis, fissile material control | dose calculation, exposure assessment, radiation hazard evaluation |
| Relacionados | 5 | 5 |
| Resumen≠ | 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. |
| ScholarGateConjunto de datos ↗ |
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