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The mechanisms responsible for fission gas release events are discussed.
The fission gas release increased with the increase of burnup.
The description of intra-granular fission gas behaviour is a fundamental part of any model for the prediction of fission gas release and swelling in nuclear fuel.
and analysis of fission gas release for three individual capsules in two separate experiments.
This paper focuses on the modelling of fission gas release in mixed oxide fuel.
Fission gas release and swelling behavior is described by the OGRES and NEFIG models.
Measurements revealed three distinct fission gas release events for the samples from 400 to 700 °C, as well as a number of minor fission gas releases below and above this temperature range.
The role of uncertainties in fission gas behavior calculations as part of engineering-scale nuclear fuel modeling is investigated using the BISON fuel performance code with a recently implemented physics-based model for fission gas release and swelling.
The fission gas removal system plays a critical role in the development of the Thorium Molten Salt reactors.
The correlation can be used by reactor designers to estimate fission gas release from postulated failed fuel in HTGR cores.
Fission gas release in FBR MOX fuel pins irradiated to high burnup was studied as a function of burnup.
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