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5 - Safety

Published online by Cambridge University Press:  05 February 2014

Anthony M. Judd
Affiliation:
United Kingdom Atomic Energy Authority
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Summary

Safety and Design

The designer of a fast reactor, just like the designer of any other engineering enterprise, has to take into account what might happen if something goes wrong. He or she has to make sure that whatever happens the risk of injury – either to the operating staff or the general public – or of damage to property, is very slight.

There are basically two ways of making a reactor safe. First the overall design concept is chosen so that it is inherently safe. That is to say that for a number of possible accidents the design is such that the reactor behaves safely and damage does not spread even if no protective action, automatic or deliberate, is taken. But it is not possible to guard against all accidents in this way, however well the overall design is chosen. The second way to make the reactor safe is to incorporate protective systems. These are devices designed specifically to prevent the damaging consequences of accidents. A protective system can be active, such as an automatic shutdown system, or passive, such as a containment barrier.

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Publisher: Cambridge University Press
Print publication year: 2014

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References

Aitken, A. (1977) Quantitative Approach to Reliability of Control and Instrumentation Systems, pp 73–107 in Farmer, F. R. (ed.) Nuclear Reactor Safety, Academic Press, New YorkCrossRefGoogle Scholar
Bethe, H. A. and Tait, J. H. (1956) An Estimate of the Order of Magnitude of the Explosion when the Core of a Fast Reactor Collapses Report UKAE-RHM (56) 113, HMSO, LondonGoogle Scholar
Board, S. J., Hall, R. W. and Hall, R. S. (1975) Detonation of Fuel-Coolant Explosions, Nature, 254, 319–321CrossRefGoogle Scholar
Briggs, A. J., Fishlock, T. P. and Vaughan, G. J. (1979) A Review of Progress with Assessment of MFCI Phenomenon in Fast Reactors following the CSNI Specialist Meeting in Bournemouth, April 1979, pp 1502–2511 in Fast Reactor Safety Technology, Volume 3, American Nuclear Society, LaGrange Park, Illinois, USAGoogle Scholar
Broomfield, A. M. and Smedley, J. A. (1979) Operating Experience with Tube to Tubeplate Welds in PFR Steam Generators, pp 3–18 in Welding and Fabrication in the Nuclear Industry, British Nuclear Energy Society, LondonCrossRefGoogle Scholar
Farmer, F. R. (1967) Siting Criteria, a New Approach, pp 303–324 in Containment and Siting of Nuclear Power Plants, International Atomic Energy Agency, ViennaGoogle Scholar
Farmer, F. R. (Ed.) (1977) Nuclear Reactor Safety, Academic Press, New York
Fuchs, K. (1946) Efficiency for a Very Slow Assembly Report LA-596, US Department of Energy, Washington, DCGoogle Scholar
Graham, J. (1971) Fast Reactor Safety, Academic Press, New YorkGoogle Scholar
Hans, R. and Dumm, K. (1977) Leak Detection of Steam or Water into Sodium in Steam Generators for LMFBRs, Atomic Energy Review, 15, 611–699Google Scholar
Henry, R. E. and Fauske, H. K. (1975) Energetics of Vapour Explosions Report 75-HT-66, American Nuclear Society, LaGrange Park, Illinois, USAGoogle Scholar
Hicks, E. P. and Menzies, D. C. (1965) Theoretical Studies on the Fast Reactor Maximum Accident, pp 654–670 in Report ANL 7120 Safety, Fuels and Core Design in Large Fast Power Reactors, US Department of Energy, Washington, DCGoogle Scholar
Kinchin, G. H. (1979) Design Criteria, Concepts and Features Important to Safety and Licensing, pp 1–8 in Fast Reactor Safety Technology, Volume 1, American Nuclear Society, LaGrange Park, Illinois, USAGoogle Scholar
Kirsch, D. (1974) Investigations on the Flow and Temperature Distribution Downstream of Local Blockages in Rod Bundle Assemblies, Nuclear Engineering and Design, 31, 266–279CrossRefGoogle Scholar
Kramer, W. K., Schleiseik, K., Schmidt, L., Vanmassenhove, G. and Verwimp, A. (1979) In-Pile Experiments “Mol 7C” Related to Pin to Pin Failure Propagation, pp 473–482 in Fast Reactor Safety Technology, Volume 1, American Nuclear Society, LaGrange Park, Illinois, USAGoogle Scholar
Lewis, E. E. (1977) Nuclear Power Reactor Safety, Wiley-Interscience, New YorkGoogle Scholar
Plein, H. G., Lipinski, R. J., Carlson, G. A. and Varela, D. W. (1979) Summary of the First Three In-Core PAHR Molten Fuel Pool Experiments, pp 356–359 in Fast Reactor Safety Technology, Volume 1, American Nuclear Society, LaGrange Park, Illinois, USAGoogle Scholar
Schleisiek, K. (1974) Sodium Experiments Related to Local Coolant Blockages in Test Assemblies Similar to Fuel Assemblies Report KFK 1914, Karlsruhe Institute of Technology (in German)Google Scholar
Smedley, J. A. (1976) Implications of Small Water Leak Reactions on Sodium-Heated Steam Generator Design, Journal of the British Nuclear Energy Society, 15, 153–156Google Scholar
Smidt, D. and Schleisiek, K. (1977) Fast Breeder Safety against Propagation of Local Failures,Nuclear Engineering and Design, 40, 393–402CrossRefGoogle Scholar
Smith, D. C. G., Bagley, K. Q., Gregory, C. V., Leet, G. O and Tait, D. (1978) DFR Special Experiments, pp 201–214 in Design, Construction and Operating Experience of Demonstration LMFBRs, International Atomic Energy Agency, ViennaGoogle Scholar
Tregonning, K., Mackay, A. and Buxton, K. (1975) Studies of a Mechanism for Material Wastage by Sodium-Water Reaction Jets, Journal of the British Nuclear Energy Society, 14, 77–82Google Scholar
Tucek, K., Carlson, J. and Wider, H. (2005) Comparison of Sodium and Lead-Cooled Fast Reactors Regarding Severe Safety and Economic Issues Report ICONE13–5037, Proceedings of the 13th International Conference on Nuclear Engineering, CNS, BeijingGoogle Scholar
United States Nuclear Regulatory Commission (1975) Reactor Safety Study, Appendix 1: Accident Definition and Use of Event Trees Report WASH 1400, USNRC, Washington, DCGoogle Scholar
Waltar, A. E. and Reynolds, A. B. (1981) Fast Breeder Reactors, Pergamon, New YorkGoogle Scholar

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  • Safety
  • Anthony M. Judd, United Kingdom Atomic Energy Authority
  • Book: An Introduction to the Engineering of Fast Nuclear Reactors
  • Online publication: 05 February 2014
  • Chapter DOI: https://doi.org/10.1017/CBO9781139540858.007
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  • Safety
  • Anthony M. Judd, United Kingdom Atomic Energy Authority
  • Book: An Introduction to the Engineering of Fast Nuclear Reactors
  • Online publication: 05 February 2014
  • Chapter DOI: https://doi.org/10.1017/CBO9781139540858.007
Available formats
×

Save book to Google Drive

To save content items to your account, please confirm that you agree to abide by our usage policies. If this is the first time you use this feature, you will be asked to authorise Cambridge Core to connect with your account. Find out more about saving content to Google Drive.

  • Safety
  • Anthony M. Judd, United Kingdom Atomic Energy Authority
  • Book: An Introduction to the Engineering of Fast Nuclear Reactors
  • Online publication: 05 February 2014
  • Chapter DOI: https://doi.org/10.1017/CBO9781139540858.007
Available formats
×