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Site Survey and Site Selection for Nuclear Installations

SSG-35

Site Survey and Site Selection for Nuclear Installations

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SSG-35

Site Survey and Site Selection for Nuclear Installations

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Footnotes
1INTERNATIONAL ATOMIC ENERGY AGENCY, Site Survey for Nuclear Power Plants, Safety Series No. 50-SG-S9, IAEA, Vienna (1984).
2The term ‘nuclear installation’ includes: nuclear power plants; research reactors (including subcritical and critical assemblies) and any adjoining radioisotope production facilities; spent fuel storage facilities; facilities for the enrichment of uranium; nuclear fuel fabrication facilities; conversion facilities; facilities for the reprocessing of spent fuel; facilities for the predisposal management of radioactive waste arising from nuclear fuel cycle facilities; and nuclear fuel cycle related research and development facilities.
3For sites at which nuclear installations of different types are collocated, particular consideration should be given to the use of a graded approach so that siting evaluation is commensurate with the approach needed for the most potentially hazardous nuclear installations.
4Site evaluation is defined as the analysis of factors at a site that could affect the safety of a facility or activity on that site. This includes site characterization and consideration of factors that could affect safety features of the facility or activity so as to result in a release of radioactive material and/or could affect the dispersion of such material in the environment, as well as population and access issues relevant to safety (e.g. feasibility of evacuation, location of people and resources) [10].
5The site characterization stage is further subdivided into: site verification, in which the suitability of the site to host a nuclear installation is verified mainly according to predefined site exclusion criteria, and site confirmation, in which the characteristics of the site necessary for the purposes of analysis and detailed design are determined [10].
6Other terms are used in some States, e.g. preliminary safety case.
7In the pre-operational stage, studies and investigations begun in the previous stages are continued after the start of construction and before the start of operation of the nuclear installation, to complete and refine the assessment of site characteristics. The site data obtained allow a final assessment of the simulation models used in the final design.
8At the operational stage, appropriate safety related site evaluation activities are carried out over the operating lifetime of the nuclear installation, mainly by means of monitoring and periodic safety review.
9The necessary extent of data collection and analysis cannot be specified in this Safety Guide since they are likely to be specific to the State and to the site concerned.
10A cliff edge effect in a nuclear installation is an instance of severely abnormal system behaviour caused by an abrupt transition from one system status to another following a small deviation in a system parameter, and thus a sudden large variation in system conditions in response to a small variation in an input.
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Tags applicable to this publication

  • Publication type:Specific Safety Guide
  • Publication number: SSG-35
  • Publication year: 2015
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