Experimental evaluation of structural integrity of scram release electromagnet

•The structural integrity of scram release electromagnet is evaluated against thermal shocks.•A simple test facility, employed for simulating the thermal shocks in a typical FBR, is presented.•The cold shock experienced by electromagnet during scram is simulated.•The testing qualified electromagnet...

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Veröffentlicht in:Nuclear engineering and design 2014-07, Vol.274, p.90-99
Hauptverfasser: Patri, Sudheer, Ruhela, S.P., Punniyamoorthy, R., Vijayashree, R., Chandramouli, S., Kumar, P. Madan, Rajendraprasad, R., rao, P. Vijayamohana, Narmadha, S., Sreedhar, B.K., Rajan, K.K.
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Sprache:eng
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Zusammenfassung:•The structural integrity of scram release electromagnet is evaluated against thermal shocks.•A simple test facility, employed for simulating the thermal shocks in a typical FBR, is presented.•The cold shock experienced by electromagnet during scram is simulated.•The testing qualified electromagnet for 11.6yr of reactor operation. Prototype fast breeder reactor (PFBR), under construction at Kalpakkam, India, plays an important role in the commercialisation of fast breeder reactors (FBR) in India. It consists of two independent, fast acting and diverse shutdown systems. An electromagnet (EM) immersed in sodium acts as scram release device for the second shutdown system of prototype fast breeder reactor. The inside of EM is sealed from the sodium to achieve the required response time and to prevent the exposure of EM coil to sodium. As the EM response time is an important parameter for reactor safety, the integrity of EM is to be maintained under all anticipated loadings. The EM experiences thermal shocks and thermal stresses during reactor transients such as scram. The dissimilar weld joint present in EM is more susceptible to fatigue failure due to these thermal stresses. Failure of weld joint results in the entry of sodium into the EM, increasing its response time with associated safety implications. In this connection, the structural integrity of EM against thermal shocks was experimentally evaluated in Thermal Shock Test Facility. The EM was subjected to 1000 cycles of thermal shocks, which constitutes 29% of total number of shocks required to qualify the EM for 40 years of reactor operation, thus qualifying it for 11.6yr of reactor operation. The testing has enhanced the confidence level for safe and reliable operation of EM of DSRDM in PFBR. The testing not only qualified the EM for use in reactor but also provided input for licensing the erection of DSRDM on reactor pile. Moreover, it provided a direction for qualifying similar components in future.
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2014.03.033