Component Category: -Decay heat removal systems
2 documents found
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Heat transfer calculations on the KNK II emergency cooling system Waermetechnische Rechnungen zum KNK II Notkuehlsystem
Vossebrecker, H.;Groenefeld, GINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--76.130 - German - 1976
Abstract: The Licensing Authority had demanded that in case of the change of the KNK thermal core into a fast core the decay heat removal system must be improved by a diverse and spatially separated emergency cooling system. In order to meet this requirement an existing nitrogen system of the facility is extended in such a manner that the decay heat will be removed by a nitrogen flow passing through the gap between reactor vessel and guard vessel. The heat transport from the core to the vessel is accomplished by natural convection flow rates which are generated by density differences between the hot core subassemblies, the reflector subassemblies and other passages between the upper and the lower plenum. The calculations show that the maximum temperatures in the core do not reach the sodium boiling-point. The maximum vessel temperature is 673 deg. C. In this report the function of the emergency cooling system and the methods of calculation are described, the input data and the results are stated and it is shown that the calculated temperatures are conservative
Key words: after-heat removal;boiling points;eccs;heat transfer;knk-2 reactor;natural convection;reactor cores;reactor vessels;safety analysis;sodium
R&D Category: Safety aspects
display the document: 34087422.pdf
Dynamic simulation of the air-cooled decay heat removal system of the German KNK-II experimental breeder reactor
Schubert, B.KBrookhaven National Lab., Upton, NY (USA)
NUREG/CR--3910 - English - 1984
Abstract: A Dump Heat Exchanger and associated feedback control system models for decay heat removal in the German KNK-II experimental fast breeder reactor are presented. The purpose of the controller is to minimize temperature variations in the circuits and, hence, to prevent thermal shocks in the structures. The basic models for the DHX include the sodium-air thermodynamics and hydraulics, as well as a control system. Valve control models for the primary and intermediate sodium flow regulation during post shutdown conditions are also presented. These models have been interfaced with the SSC-L code. Typical results of sample transients are discussed
Key words: after-heat removal;control systems;feedback;heat exchangers;knk-2 reactor;simulation
R&D Category: Safety aspects
display the document: 16058473.pdf