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The Joint European Torus (JET) operates using deuterium as a fuel but has also operated in D–T mode where the fusion reaction is fuelled by deuterium and tritium. To justify the safety of the experiments, safety reports are produced and approved. The safety case has recently undergone a periodic safety review and preparations are being made to undertake a tritium campaign in 2015. To provide information regarding the compatibility between reactor-grade plasma and the materials facing the plasma, an “ITER-like wall” was installed in JET comprising beryllium first wall tiles, solid tungsten and CFC tungsten coated tiles in the divertor region. In the prospect of the next D–T campaign with the new wall, the following areas of specialist assessment have been identified: • Engineering fit for purpose assessment of key safety related equipment, • Human factor assessment of key safety management requirement, This paper will present a status report of these assessments and the methodology applied. Along with the results of a loss of coolant accident (LOCA) analysis using the CEA developed thermal hydraulics code CATHARE 2 V25-2. |
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