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Cuestiones de diseño relacionadas con la protección radiológica en centrales nucleares

50-SG-D9

Also available in:

Spanish STI/PUB/687 92-0-323686-4
22.50 1986

Description

This guide provides principles and practical details on the provisions to be made in the design of nuclear power plants to protect site personnel and the general public from ionizing radiation during operational states and accident conditions. The dose limitation systems, including the ALARA principle, are described as the basis for appropriately addressing the radiation protection features in nuclear power plant design.
Contents: Introduction; Basic concepts of radiation protection; Radiation protection aspects in design; Sources of radiation during normal operation; Sources of radiation under accident conditions; Protection of site personnel during operational states; Protection of site personnel under accident conditions; Protection of the public under accident conditions; Guidelines for determining radiation dose rates during operational states; Considerations for determining potential doses under accident conditions; Monitoring of radiation during operational states; Monitoring of radiation under accident conditions; Process monitoring for radiological protection; Auxiliary facilities; Annex I. Radioactive releases and exposure limits for members of the public; Annex II. Depressurization accidents in AGR reactors; Annex III. Zoning of nuclear power plants; Annex IV. Methodology for source and flux calculations; Annex V. Statement on the role of quantitative optimization in nuclear power plant radiation protection.

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