3 - Reactor Core
Published online by Cambridge University Press: 05 February 2014
Summary
Introduction
Having described the neutron physics of a fast reactor in Chapter 1 and the behaviour of the fuel elements in Chapter 2, in this chapter we discuss the engineering of the core of a power-producing fast reactor. The three following sections deal with heat transfer, materials and structure.
Heat transfer comes first because the dimensions of the fuel elements and of the core are determined mainly by the demands of heat transfer. The fuel elements have to be of the right dimensions to transfer heat to the coolant at the required rate without overheating. The core has then to be large enough to allow enough coolant to flow through it to take the heat away. This section deals mainly with liquid metal coolants.
Once themain dimensions are fixed the form of the core is determined by the properties of the materials of which it is made, and in particular by the way these properties are affected by neutron irradiation and exposure to the coolant. The structure of the core has then to be designed within these constraints to hold the fuel in place, to allow it to be changed when necessary, to distribute the coolant flow correctly, and to provide for the control rods.
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- An Introduction to the Engineering of Fast Nuclear Reactors , pp. 150 - 191Publisher: Cambridge University PressPrint publication year: 2014
References
and (2007) Lead-Cooled Fast Reactor Systems and the Fuels and Materials Challenges, Science and Technology of Nuclear Installations, article ID 97486
, and (1973) Irradiation Embrittlement of Austenitic Stainless Steels, pp 143–153 in Irradiation Embrittlement and Creep in Fuel Cladding and Core Components, British Nuclear Energy Society, LondonCrossRefGoogle Scholar
., , , , , and (1978) Void Swelling and Microstructural Changes in Fuel Pin Cladding and Unstressed Specimens irradiated in DFR, pp 479–508 in Radiation Effects in Breeder Reactor Structural Materials, American Society of Mining Engineers, New YorkGoogle Scholar
(1968) Heat Transfer to Liquid Metals flowing In-line through Unbaffled Rod Bundles, pp 139–168 in Heat Transfer in Rod Bundles, American Society of Mechanical Engineers, New YorkGoogle Scholar
, , and (1975) A UKAEA Evaluation of Displacement Damage Models for Iron, Nuclear Engineering and Design, 33 82–90CrossRefGoogle Scholar
and (1961) Analytical Study of Heat Transfer Rates for Parallel Flow of Liquid Metals through Tube Bundles, Journal of the American Institute of Chemical Engineering, 7, 107–112CrossRefGoogle Scholar
and (1978) Thermodynamic and Fluiddynamic Aspects in Optimizing the Design of Fast Reactor Subassemblies, pp 133–139 in Optimisation of Sodium-Cooled Fast Reactors, British Nuclear Energy Society, LondonGoogle Scholar
, and (2010) Structure of Oxide Nanoparticles in Fe-16Cr MA/ODS Ferritic Steel Lawrence Livermore National Laboratory report LLNL-JRNL-427350
and (1974) Irradiation Creep in Some Austenitic Stainless Steels, Nimonic PE16 Alloy, and Nickel, pp 169–188 in Creep Strength in Steel and High-Temperature Alloys, London, The Metals Society, LondonGoogle Scholar
, , , , and (1967) Problems in the Selection and Utilization of Materials in Sodium Cooled Fast Reactors, pp 825–849 in Fast Breeder Reactors (BNES Conference proceedings), Pergamon, OxfordCrossRefGoogle Scholar
, , and (1963) A Study of Heat Transfer to Molten Sodium in Tubes, Soviet Journal of Atomic Energy, 13, 991–994CrossRefGoogle Scholar
, and (1978) Thermal Analysis of Liquid-Metal Fast Reactors, American Nuclear Society, Hinsdale, Illinois, USAGoogle Scholar
and (1973) Corrosion and Mass Transport of Steel and Nickel Alloys in Sodium Systems, pp 257–273 in Liquid Alkali Metals, British Nuclear Energy Society,LondonGoogle Scholar
and (2007) Review of the Studies on Fundamental Issues in LBE corrosion, Journal of Nuclear Materials, 373, 351–377CrossRefGoogle Scholar
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