The Cabri International Project (CIP) investigates the ability of both uranium dioxide (UO2) and mixed-oxide fuel (MOX) pressurized-water reactor (PWR) fuels to withstand sharp power transients that would arise from rapid reactivity injection in the core, i.e. so-called reactivity-initiated accidents (RIA). The project stems from earlier Japanese and French tests conducted on high burn-up PWR fuel that, in a few instances, exhibited failure at relatively moderate levels of injected energy. CIP aims to extend the database for high burn-up fuel behaviour and, importantly, perform the majority of tests in conditions representative of PWR RIAs. The experimental programme is undertaken by the Institut de Radioprotection et de Sûreté Nucléaire (IRSN) at Cadarache, France, where the Cabri facility is located. The programme may also involve laboratories of partners relating to, e.g. fuel characterisation or post-irradiation examinations (PIEs).
CIP partners determine the test conditions where the experimental programme is regularly reviewed by the Technical Advisory Group and the project is overseen by the Steering Committee. CIP comprises twelve tests where the first two tests, CIP0-1 and CIP0-2, have been performed in the original sodium loop of the Cabri facility. The test matrix evolves as CIP progresses but an illustration is provided below.
The CIP tests are complemented by pulse-irradiation tests performed in JAEA’s Nuclear Safety Research Reactor (NSRR), e.g., Fuketa et al., (2006), J. Nucl. Sci. Technol. 43(9).
The project began in March 2000. In 2002, CIP0-1 and CIP0-2 were performed using fuel of very high burn-up with M5 and Zirlo claddings. Post-irradiation examinations (PIEs) involving destructive examinations in 2004 investigated, in particular, the effect of hydrogen on cladding properties. Since then, the IRSN has been engaged in a programme of conversion to a water loop and considerable upgrading of the facility. In October 2015, following the loading of new fuel in 2014, the French regulator authorised operation of the refurbished reactor and the first criticalities of the core were produced a few days later. Low power tests from October 2015 to June 2016 allowed complete neutronic characterisation of the core. In 2015-16, qualification of the experimental equipment was completed, in particular the imagery and spectroscopy measurement station, as well as the hodoscope which recorded its first neutrons, and the pressurised-water loop that was also qualified at 280°C and 155 bars. In the last quarter of 2016, the new core achieved its first plateaus at high power, i.e. 5-23 MW, which allowed further instrument qualification including the neutron chambers that provide online measurement of the reactor power. Power-transient tests started in January 2017. The current aim is to request safety authorisation of the first water loop test and perform it before the end of 2017. Subsequently, the IRSN will be in a position to perform two tests per year where rodlets for the first five tests are already prepared.
The data abstract is public.
January 2016 to March 2018
~ EUR 74 million
Last reviewed: 27 February 2017