Fission gas release in FBR MOX fuel irradiated to high burnup

Development of CAP process for fabrication of ThO2–UO2 fuels Part II: Characterization and property evaluation

“…The microstructure of the fuel is intimately related to the behavior of the fission gases. The improvement in plasticity and fission gas release can be attained by modifying the microstructures during fabrication [2][3][4][5][6]. The conventional process for nuclear ceramics fabrication consists of a number of stages including calcination, milling, incorporating additives, pressing, drying and densification.…”

Dimensional measurements on 112GWd/t irradiated MOX fuel pins using X-ray radiography

“…The fuelstack length measurement made on these fuel pins by neutron radiography and gamma scanning methods showed an average stack length increase of 1.3% and 1.2%, respectively (Venkiteswaran and et al, 2014). The lower volumetric fuel swelling is attributed to the combination of various factors such as low fuel smear density (76% of theoretical density), release of volatile fission products and high fission gas release in MOX fuel at this burn-up level (Venkiteswaran and et al, 2014;Maeda et al, 2005).…”

Specific low temperature release of 131Xe from irradiated MOX fuel

“…Samples of irradiated MOX were analysed at ITU. A detailed description of the technique and of the apparatus can be found elsewhere [1,9]. The temperature range of the experiments was 500-2650 K. All tests were performed under vacuum with a heating rate of 10 K/min.…”

“…Fission gas release (FGR) is a key issue affecting in-pile safety and performance of MOX fuel [1]. A joint ITU-CRIEPI research programme has started with the aim of clarifying fission gas release mechanisms from MOX fuel from the experimental and modelling points of view.…”