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  1. 41
    Published 2012
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    OECD
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    International Structure for Decommissioning Costing (ISDC) of Nuclear Installations /
  2. 42
    Published 2021
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    Spallation materials technology : special topic volume with invited peer-reviewed papers only /
  3. 43
    Published 2020
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    Reload design and core management in operating nuclear power plants : experiences and lessons learned /
  4. 44
    Published 1967
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    ICE Premier Collection
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    The physics problems in thermal reactor design : proceedings of an international conference at the Institution of Civil Engineers, London SWl, 27-29 June 1967.
  5. 45
    Published 2013
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    Status report on structural materials for advanced nuclear systems.
  6. 46
    Published 2009
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    Build your own nuclear reactor.
  7. 47
    Published 2021
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    Structural materials for heavy liquid metal cooled fast reactors : proceedings of a technical meeting /
  8. 48
    Published 2023
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    OECD
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    The effect of temperature on the neutron multiplication factor for pressurised water reactor fuel assemblies : a temperature analysis benchmark.
  9. 49
    Published 2009
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    Nuclear power: "a tough debate" /
  10. 50
    Published 1972
    Ebook
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    ICE Premier Collection
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    Voids formed by irradiation of reactor materials : proceedings of the British Nuclear Energy Society European conference held at Reading University on 24 and 25 March 1971, /
  11. 51
    Published 2014
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    OECD
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    Minor actinide burning in thermal reactors : a report by the working party on scientific issues of reactor systems /
  12. 52
    Published 1989
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    OECD
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    Proceedings of a Specialists' Meeting on In Core Intrumentation and Reactor Assessment : Cadarache, France, 7th-10th June 1988 = Compte rendu d'une réunion de spécialistes sur l'instrumentation et l'évaluation de l'état du coeur des réacteurs nucléaires : Cadarache, France, 7-10 juin 1988.
  13. 53
    Published 2020
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    Engineering separations unit operations for nuclear processing /
  14. 54
    by Lee, John C., 1941-
    Published 2020
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    Nuclear reactor physics and engineering /
  15. 55
    Published 2020
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    Understanding and prediction of thermohydraulic phenomena relevant to supercritical water cooled reactors (SCWRs) : final report of a Coordinated Research Project /
  16. 56
    Published 2020
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    Pathways to energy from inertial fusion : structural materials for inertial fusion facilities /
  17. 57
    Published 2020
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    Reliability data for research reactor probabilistic safety assessment : final results of a Coordinated Research Project /
  18. 58
    Published 2020
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    Material properties of unirradiated uranium-molybdenum (U-Mo) fuel for research reactors /
  19. 59
    Published 2002
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    OECD
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    Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs : Paris, France, 18-20 February 2002 /
  20. 60
    by Zohuri, Bahman, Fathi, Nima
    Published 2015
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    Springer eBooks
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    Thermal-hydraulic analysis of nuclear reactors /
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