Персона: Савандер, Владимир Игоревич
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Investigation of using U-233 in thorium base instead of conventional fuel in Russian PWR by SERPENT Code
© Published under licence by IOP Publishing Ltd.In this work, the fuel assembly of type TVS-2006, which is used in Russian reactor VVER-1200, is considered. A proposed fuel of Thorium and Uranium-233 ((Th232+U233)O2 has been investigated to replace the fuel currently used (U238 as a fertile and U235 as fissile). This has been done in order to compare the; conversion ratio, reproduction factor (?), burnup, effective delayed neutrons fraction (ßeff), Minor Actinides (MA) inventory, and Temperature coefficients of reactivity. The calculations performed using the Monte Carlo code (SERPENT-2.31) to analyze and compare the two fuels. Results showed that using U-233 in the Thorium base will considerably increase the reactivity at the Beginning Of Cycle (BOC), increase the conversion ratio, and burn up. Besides, the safety parameters for the proposed Th-based fuel, in general, lower than that for Low Enriched Uranium (LEU) but still acceptable.
Use of erbium as a burnable absorber for the VVER reactor core life extension
Analysis of the Efficiency of Applying Core Lifetime Extension on Foreign NPPs with VVER-Type Reactors
The efficiency of applying extended operating periods on foreign NPPs under construction with VVER-type reactors designed in Russia has been analyzed in the cases of the temporary storage of spent fuel assemblies on site of the NPP and their transportation to Russia for long-term storage. In order to reduce the flow of spent fuel assemblies for temporary storage, increasing the enrichment of the makeup fuel has been considered, which leads to increases in the fuel burnup and operating period.
Use of erbium as a burnable absorber for the VVER reactor core life extension ИСПОЛЬЗОВАНИЕ ЭРБИЯ В КАЧЕСТВЕ ВЫГОРАЮЩЕГО ПОГЛОТИТЕЛЯ В РЕАКТОРАХ ТИПА ВВЭР ПРИ РАБОТЕ НА УДЛИНЕННЫХ КАМПАНИЯХ
© 2020 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved.The paper presents the results of a computational and theoretical analysis dealing with the use of erbium as a burnable absorber in VVER$type reactors. Partial refueling options for the reactor life extension (to a year and a half to two years) are considered, the refueling ratio being equal to three for the former and to two for the latter. Erbium is expected to be present in all fuel elements in the FA with the same weight content. The influence of the erbium weight content on such reactor and fuel neutronic characteristics as burn$up, reactivity coefficients, residual volume of «liquid control», and volumes of the liquid radioactive waste formed has been estimated. Calculations were performed based on a simplified refueling model without FA reshuffling. An infinite mesh of polycells, consisting of FAs with different in$core times, was considered. The neutron escape from the core was taken into account through the selection of the critical value KҐ at the end of life. Erbium does not burn up altogether for the core life which affects the fuel burn$ up reduction as compared with the liquid system for excessive reactivity compensation. The reduction is 0.7% per 0.1% of the erbium weight load in the fuel element. This, however, also reduces the maximum content of the boron absorber in the coolant and the accumulation of LRW in the ratio of 5% per 0.1% of the erbium weight load. Erbium influences the spectral component of the coolant temperature reactivity coefficient which turns out to be negative even with a minor weight fraction in fuel and the decrease in the boron absorber fraction leads to a positive value of the density reactivity coefficient. As the result, the total coolant temperature reactivity coefficient has a negative value throughout the life.