Studsvik Cladding Integrity Projec (SCIP) is a prestigious OECD project successfully operated by Studsvik since 2004. The project is truely international with participants from Europe, Russia, China, Japan, the US and Korea.
And now, in the SCIP III, the fuel fragmentation, relocation and release during off-normal temperature transient, LOCA, the fuel and cladding response to transient leading to cladding overheating, and the mitigating effect on PCI of the ramp rate and oxygen, will be studied. All of this still keeping the support of the modelling.
In the project different cladding materials are tested, mainly by means of microscopy studies, mechanical testing, semi-integral test and reactor tests. It is conducted in the form of experiments, studies of fundamental mechanisms, development of suitable testing methods and knowledge transfer.
The results are used to support the nuclear community, vendors, authorities, utilities and laboratories in assessing margins and increasing the nuclear fuel safety.