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[en] The contribution of fuel assemblies to the response of ex-core detectors does not only depend on the power, but also on the position of the given assemblies in the reactor core. The weight of the inner fuel assemblies is several orders of magnitude lower than the outer ones. Therefore, the signal of the ex-core detectors for a given reactor power is strongly influenced by the spatial power distribution and indirectly by the parameters which determine the distribution, such as load pattern, time elapsed, etc. The aim of the work is to describe the modelling and the methodology for calculation of the spatial weight function of ex-core detectors for the WWER-440 reactor type using Monte Carlo transport code system MCNP-4C2, taking into account different operational parameters such as power, burn-up, boric acid concentration, position of the control assembly group No 6, etc. The spatial weight function provides relationship between the spatial neutron flux density distribution or the fission density distribution in the reactor core and the ex-core detectors. The weight function is possible to define in various ways in dependence on solved problem. In this case the function gives the average number of reactions occurred in the detector for one neutron born with Watt fission spectra created in the twentieth of a fuel pin in different reactor core position. From the definition of the weight function follows that the response of the ex-core detector is given by the weight function and the fission density distribution function product and its integration over the reactor core or its part. The spatial weight function will be used for interpretation of reloads startup rod drop measurements, assessment of the ex-core detectors response at deep subcritical reactor stage and for other applications (Authors)
Source
Vidovszky, Istvan (ed.) (Kiadja az MTA KFKI Atomenergia Kutatointezet, H-1525 Budapest 114, POB 49 (Hungary)); VUJE, Inc., 918 64 Trnava (Slovakia); Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, 81219 Bratislava (Slovakia); KFKI Atomic Energy Research Institute, Reactor Analysis Laboratory, H-1525 Budapest 114, POB 49 (Hungary); NPP Dukovany, 675 50 Dukovany (Czech Republic); Institute State Scientific and Technical Center for Nuclear and Radiation Safety, 35-37 Radgospna street, 03142 Kyiv-142 (Ukraine); Kozloduy NPP plc, Kozloduy 3321 (Bulgaria); NPP Bohunice, Jaslovske Bohunice (Slovakia); Nuclear Research Institute Rez plc, CZ-250 68 Husinec-Rez, cp.130 (Czech Republic); Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest XI, Mueegyetem rkp. 9, 1111 (Hungary); 753 p; ISBN 963-372-633-4; 
; Oct 2006; p. 345-352; 16. Atomic Energy Research Symposium on WWER Physics and Reactor Safety; Bratislava (Slovakia); 25-29 Sep 2006; Also available from VUJE, Inc., Okruzna 5, 918 64 Trnava (SK); 3 refs.; 5 figs.
; Oct 2006; p. 345-352; 16. Atomic Energy Research Symposium on WWER Physics and Reactor Safety; Bratislava (Slovakia); 25-29 Sep 2006; Also available from VUJE, Inc., Okruzna 5, 918 64 Trnava (SK); 3 refs.; 5 figs.