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AbstractAbstract
[en] In nuclear installations main requirement is to obtain corresponding nuclear safety in all operation conditions. From the nuclear safety point of view is commissioning and start-up after reactor refuelling appropriate period for safety systems verification. In this paper, methodology, performance and results of neutron flux measurements systems validation is presented. Standard neutron flux measuring chains incorporated into the reactor protection and control system are used. Standard neutron flux measuring chain contains detector, preamplifier, wiring to data acquisition unit, data acquisition unit, wiring to display at control room and display at control room. During reactor outage only data acquisition unit and wiring and displaying at reactor control room is verified. It is impossible to verify detector, preamplifier and wiring to data acquisition recording unit during reactor refuelling according to low power. Adjustment and accurate functionality of these chains is confirmed by start-up rate (SUR) measurement during start-up tests after refuelling of the reactors. This measurement has direct impact to nuclear safety and increase operational nuclear safety level. Briefly description of each measuring system is given. Results are illustrated on measurements performed at Bohunice NPP during reactor start-up tests. Main failures and their elimination are described (Authors)
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Vidovszky, Istvan (Kiadja and KFKI Atomenergia Kutatointezet, H-1525 Budapest 114, POB 49 (Hungary)); VUJE Trnava, Inc. - Engineering, Design and Research Organization, 918 64 Trnava (Slovakia); RRC 'Kurchatov Institute', Institute of Nuclear Reactors, VVER Department, 123182 Moscow (Russian Federation); Paks NPP Ltd., 7031 Paks (Hungary); Skoda JS a.s., Orlik 266, 316 06 Plzen (Czech Republic); INRNE - Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences, Tzarigradsko Shaussee 72, Sophia 1784, (Bulgaria); UJV Rez plc, 250 68 Rez (Czech Republic); [833 p.]; ISBN 963-372-630-1;
; Nov 2003; p. 327-335; 13. Atomic Energy Research Symposium on WWER Physics and Reactor Safety; Dresden (Germany); 22-26 Sep 2003; Also available from VUJE Trnava a.s. - Engineering, Design and Research Organization, Okruzna 5, 918 64 Trnava (Slovak Republic); 7 refs., 2 figs.

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