Abstract
A review of the thermochemical and thermo-physical properties of phases that can form following the chemical interaction between sodium coolant and irradiated (U,Pu)O2 fuel in a Sodium-cooled Fast Reactor is reported in the present chapter. This critical assessment is directed towards the assessment of a particular type of accidental scenario, namely that of a cladding failure and subsequent sodium ingress into the irradiated fuel pin, and focusses on the aspects of the (U,Pu,Np,Am)O2 fuel-sodium and fission products-sodium interactions........
Original language | English |
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Title of host publication | Comprehensive Nuclear Materials |
Subtitle of host publication | Second Edition |
Publisher | Elsevier |
Chapter | 7 |
Pages | 482-519 |
Number of pages | 38 |
Edition | 2nd |
ISBN (Electronic) | 9780081028650 |
ISBN (Print) | 9780081028667 |
DOIs | |
Publication status | Published - 2020 |