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Information × Registration Number 0399U002581, 0196U007218 , R & D reports Title Analysis of VVER-type reactors nuclear safety under refueling. popup.stage_title Аналiз ядерноє безпеки реакторiв ВВЕР при перевантаженнi палива. Head Khalimonchuk V. A., Registration Date 21-06-1999 Organization State Scientific and Technical Center on Nuclear and Radiation Safety popup.description2 The results are presented as to calculation of maximum value of neutrons fluence accumulated at inner surfaceof VVER-440 reactor pressure vessel of unit 2 at Rivne NPP during 13 campaigns. For the 5th campaign comparison of fast neutrons flux density experimental and calculated values was performed with sensor activation rates. The results are presented as to calculation of neutrons fluence accumulated at inner surface of VVER-1000 unit 5 of Zaporizhya NPP value obtained on a basis of operational data gained for the early five compaigns of power unit. The method is presented as to parameterization of neutron and phisical constants used in the program DYN3D. The study was performent as to impact of parameterization of neutron and physical constants method upon accuracy of density and temperature reactivity coefficients identification based upon experimental values of reactivity. The de4pendents of density and temperature reactivity coefficients under reactor output increasing above minimum controlled l evel was studied for the fresh designed VVER-1000 reactor fueling. Product Description popup.authors popup.nrat_date 2020-04-03 Close