Abstract
The extensive experience with the thermal reactor core materials (uranium dioxide, boron carbide, and stainless steel) has provided the basis for LMFBR core materials development. However, as noted in Chapter 1, the LMFBR fuel system must survive a much more hostile environment than the LWR fuel system with respect to temperature and fast neutron fluence. Typical fuel rod powers of 40 to 90 kW/m (compared to a maximum of ∼40 kW/m in LWRs) yield fast neutron fluences of ~2 × 1027 n/m2 (E > 0.1 MeV), or -90 dpa, with maximum cladding temperatures of the order of 920 K (Fig. 3-1). These more extreme conditions are manifested in more profound chemical and microstructural changes in the fuel and cladding; for instance, neither fission gas release approaching 100% nor void swelling of cladding are observed in LWR fuel rods, but they are normal occurrences in some LMFBR fuel systems and must therefore be accounted for in design. Similar allowances, although of a lesser nature, have had to be made in the LMFBR control rod design.
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Roberts, J.T.A. (1981). LMFBR Core Materials. In: Structural Materials in Nuclear Power Systems. Modern Perspectives in Energy. Springer, Boston, MA. https://doi.org/10.1007/978-1-4684-7194-6_3
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