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Extra info for Advanced Containment Systems for Next-Gen Water Reactors (IAEA TECDOC-752)

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SYSTEMS AND COMPONENTS TO IMPROVE LEAKTIGHTNESS A primary requirement for all proposed containment is obviously focussed on primary containment leaktightness in all considered design conditions. In recent years, two different trends in this respect may be noted. 5%-15% per day for BWR containments) believing that this is achievable with current technology based on operating 46 -fr LEGEND H/F: HEPA F i l t e r C/F: Charcoal Fi l i e r Compressed Gas Tank

G. France-CEA TRIREM, Italy-ENEA activities) [30, 31, 33]. 3. EXPERIMENTAL RESEARCH Experimental efforts in the area of ALWRs can be divided into three groups: behaviour of containment components and structures under severe accidents conditions, phenomenological research, system and components testing. 1. g. g. Sandia l/6th reinforced concrete, Sandia l/8th metallic, Sizewell B l/10th prestressed concrete [32]). The goal of these experiments is not only determine the ultimate failure loads but also to evaluate the effect of such factors as: • effect of reinforcement and prestressing, • effect of random defects, 57 • effect of the size and location of containment penetrations.

It should be pointed out that some FCI models imply a greater probability of in-vessel steam explosions if the vessel is at low pressure at the time of the event. This situation is much more likely in many next generation reactors since primary system depressurization is part of the prevention strategy. It should be pointed out, however, that in this case static pressure load should not be added in the evaluation of vessel integrity, and, on the other hand, this event is not likely to cause containment failure.

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Advanced Containment Systems for Next-Gen Water Reactors (IAEA TECDOC-752)


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