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-Views of the main systems in the JHR facility and view of the reactor core.  

-Views of the main systems in the JHR facility and view of the reactor core.  

Source publication
Conference Paper
Full-text available
Before their uses in industrial nuclear power plants (NPP), materials and fuel have to follow a long qualification process with different stages of screening, selection, qualification, optimization, processing, lifetime assessment and safety tests. These studies are most of the time associated with a complex multi-physical modelling of the material...

Contexts in source publication

Context 1
... the reactor building, the reactor pool is surrounded by several cubicles to receive instrumentation and control systems of each irradiation devices, linked by a system of fluid pipes and cables. The figure 1 presents the whole of the system. ...
Context 2
... reflector can also receive devices with 20 fixed positions, mainly of 100mm diameter but there will be one location of 200mm diameter. On figure 1, we can also see 6 water channels distributed around the reflector, where displacement systems will receive specific devices, a priori dedicated for fuel irradiations. Many calculations were performed to estimate neutron flux levels, by TRIPOLI 4.7 associated with JEFF-3.1 nuclear data library and considering a start-up fuel configuration (U 3 Si 2 fuel and 70MW of core thermal power).In this configuration, the highest fast flux in the core is 3. .s ...
Context 3
... design will integrate the operational experience accumulated by the existing corrosion loops in cold laboratories at CEA and of course by the existing MTRs. A special attention will relate to the instrumentation associated with this device and will be based on the conclusions of the European program MTR+I3 [11].The design of such a loop can be divided in 3 parts on Figure 6 [12]: ...

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Citations

Article
Since 2015, within the scope of the Jules Horowitz Reactor (JHR) project a collaborative effort between CCFE in the UK and CEA in France has been undertaken to investigate concepts of test devices for the JHR suitable for the needs of fusion researchers. It is hoped that in having optimized experimental devices designed will facilitate use of the JHR by the fusion community. The project chose to focus on more instrumented test devices as it was felt that post-irradiation examination (PIE) type experiments at conventional temperatures could be undertaken with limited modifications to existing test devices. After internal exploration of the options, three potential test devices were identified; i) testing of ceramic functional materials; ii) testing at cryogenic temperatures; and iii) testing of thermo-mechanical fatigue. Each of these devices has been conceptually designed, demonstrating feasibility. This paper describes each of the conceptual designs at their current level of maturity. Future collaborative work planned between the two parties will aim to develop these devices further.