Component Category: -Secondary cooling and steam generator
3 documents found
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Examination of sodium wetted steam generator tube segments of KNK II Nachuntersuchungen natriumseitiger Dampferzeugerrohrabschnitte aus der KNK II
Adelhelm, Ch.;Borgstedt, H.UKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.14P07A - German - 1984
Abstract: After 13000 hours operation time the double walled tube No.45 of the KNK II steam generator QS2 has been exchanged and the sodium wetted surfaces and the matrix of the exposed steel 8 CrMoNiNb 9 10 have been examined. Metallographic examinations show, that at 590-770 K the bainitic-ferritic microstructure did not change. By scanning electron microscopy, emission spectroscopy (GDOS) and Auger electron spectroscopy the topography and the composition of the surface have been determined. The surface of the original material is covered by a Zn-containing Cr-enriched oxide layer. After contact with sodium the surface of the outer tube showed an oxide layer, similar to the initial surface. The outer surface of the inner tube is not oxidized, but has the same composition as the original material. Besides a small rising of the carbon level, no selective element leaching has taken place. A corrosion rate has been supposed for the inner wall of 20-30
Key words: auger electron spectroscopy;chromium additions;corrosion;emission spectroscopy;knk reactor;knk-2 reactor;metallography;microstructure;oxides;scanning electron microscopy;spectroscopy;steam generators;steel-crmo;surface properties;thin films;tubes;zirconium
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087770.pdf
Chemical operational experience with the water/steam-circuit at KNK II. Presentation at the meeting on Experience exchange on operational experience of fast breeder reactors, Karlsruhe/Bensberg/Kalkar, June 18. - 22. 1990 Chemische Betriebserfahrungen mit dem Wasser-Dampfkreislauf an der KNK II. Praesentation auf der Tagung zu Erfahrungsaustausch ueber Betriebserfahrungen Schneller Brutreaktoren, Karlsruhe/Bensberg/Kalkar, Juni 18. - 22. 1990
Grumer, UKernkraftwerk-Betriebsgesellschaft mbH (Germany)
INIS-DE-KBG--019 - German - 1990
Abstract: The availability of sodium cooled reactors depends essentially from the safety and reliability of the sodium heated steam generator. The transition from experimental plants with 12-20 MW electrical power to larger plants with 600 MW (BN-600) or 1200 MW (Superphenix) required the change from modular components to larger and compact steam generators with up to 800 MW. Defects of these large components cause extreme losses in availability of the plant and have to be avoided. In view of this request, a comprehensive test program has been performed at KNK II in addition to the normal control of the water/steam-circuit to compile all operational data on the water and steam side of the sodium heated steam generator. This paper describes the plant and the water/steam-circuit with its mode of operation. The experience with the surveillance and different methods of the conditioning are discussed in detail in this presentation
Key words: availability;fluid flow;knk-2 reactor;reactor operation;sodium;steam generators
R&D Category: any or undefined
display the document: 34087487.pdf
Tritium in the tertiary circuit of the compact sodium cooled nuclear reactor plant Karlsruhe (KNK II). Tritium im Tertiaerkreis der kompakten natriumgekuehlten Kernreaktoranlage Karlsruhe (KNK II)
Hanke, H.D.;Noppel, H.E.;Wild, HKernforschungszentrum Karlsruhe GmbH (Germany). Inst. fuer Radiochemie
KFK--4972 - German - 1991
Abstract: This report gives a compilation and documentation of all the values measured during twelve years for the experimental program. The data are presented in a stable together with the sampling time and the reactor power of the plant and are plotted together with the reactor power and the operation mode of both cold traps (primary and secondary) in a set of figures. It could be proved that all the tritium in the tertiary circuit is present in the chemical state of HTO by distillation experiments, and by repeated measurements. Therefore, the only sink of HTO in the water stream circuit are losses from the tertiary system into the gaseous waste (turbine condenser off-gas) and into the liquide waste (steam generator drainage during shutdown times). The necessary feed-water addition to the system is a fairly good measure for the losses (about 1m3/h). The source of HTO is the tritium diffusion through the steel walls of the steam generators, depending on the tritium content in the secondary circuits (influenced by the reactor power, and by the operation of the cold traps). No change in the tritium behavior was noted after the addition of hydrazine (N2H4) for water conditioning was canceled. High tritium values of about 25 Bq/ml have been measured twice, the first time in September 1980 when hydrazine was still added, the second time during April 1984, when the hydrazine treatment was already stopped for several months. The effect of cold trap operation was not always clearly detectable, but obviously the secondary cold trap was more effective than the primary trap. (orig./HP)
Key words: diffusion;feedwater;fission product release;gaseous wastes;heavy water;knk-2 reactor;radioactivity transport;reactor cooling systems;reactor operation;steam generators;tritium compounds;tritium;water chemistry
R&D Category: any or undefined
display the document: 23044278.pdf