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Jeff Place on INPO’s strategy for industry growth
As executive vice president for industry strategy at the Institute of Nuclear Power Operations, Jeff Place leads INPO’s industry-facing work, engaging directly with chief nuclear officers.
Hartwig Laue, Klaus Hermann Kerz
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 46-52
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33372
Articles are hosted by Taylor and Francis Online.
Within the framework of the licensing procedure for the SNR-300 nuclear power plant in Kalkar, Federal Republic of Germany, it is verified that the reactor vessel and its internal component parts withstand the loadings resulting from a hypothetical core disruptive accident (HCDA). The resultant high temperatures at the areas in contact with molten nuclear fuel are sufficiently reduced by the decay heat removal chain so that these component parts can withstand the mechanical forces resulting from the dead weight of the fuel and the adjacent component parts. The finite element method is used for determination of strain resulting from mechanical loadings and thermal expansion for the strength test and for evaluation of the component parts concerned according to the applicable rules for this type of accident, taking into consideration criteria and stress limit values.