TS ISO 12749-3
Nuclear energy, nuclear technologies, and radiological protection - Vocabulary - Part 3: Nuclear installations, processes and technologies
This document deals with the terminological data used in the standards regarding the standardization and promotion of good practices associated with the planning, design, construction, operation and decommissioning of installations, processes and technologies involving radioactive materials.
The vocabulary of nuclear installations, processes and technologies includes fuel cycle, ex-reactor nuclear criticality safety, analytical methodologies, transport of radioactive materials, materials characterization, radioactive waste management and decommissioning.
NOTE See Annex A for the methodology used to develop the vocabulary.
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About This Item
TS ISO 12749-3 is the third part of the TS ISO 12749 vocabulary series for nuclear energy, nuclear technologies, and radiological protection. It focuses on the terminology used for nuclear installations, processes, and technologies, helping ensure that the same concepts are understood consistently across planning, design, construction, operation, and decommissioning activities.
Rather than prescribing operating instructions, this standard organizes terminological data used in related standards and technical documentation. In practical terms, it supports a shared language for areas such as the fuel cycle, ex-reactor nuclear criticality safety, analytical methodologies, transport of radioactive materials, materials characterization, radioactive waste management, and decommissioning.
Why precise vocabulary matters in nuclear installations and processes
In the nuclear field, subtle wording differences can affect how a process, installation, or technology is interpreted in safety, logistics, waste handling, or analytical contexts. A structured vocabulary helps reduce ambiguity and supports consistent communication between engineers, specialists, regulators, and technical authors.
Main terminology areas covered in this part
- Fuel cycle and related material flows
- Ex-reactor nuclear criticality safety concepts
- Transport of radioactive materials and associated logistics terms
- Materials characterization and analytical methodologies
- Radioactive waste management and decommissioning
The document also notes an annex describing the methodology used to develop the vocabulary. That makes the structure of the term collection easier to understand, but this part should still be read as a terminology standard, not as a technical specification defining performance limits or operational requirements for nuclear facilities.
- Publication Date: 8.07.2024
- Standard Status: U (Yürürlükteki Standard/Standard)
- Publisher: TSE
- Document Language: en
- ICS Classification: 13.280 Radyasyondan Korunma ; 01.040.13 Çevre ve Sağlık Koruma, Güvenlik (Terimler); 01.040.27 Enerji ve Isı Transfer Mühendisliği (Terimler); 27.120.01 Nükleer Enerji (Genel)
- Pages: 37
- Source Standard: ISO 12749-3:2024
- International Equivalents: ISO 12749-3-EQV
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