[en] The conference papers are dealing with issues of nuclear safety and future of nuclear energy. Topic on nuclear energy problems, spent fuel disposal, RBMK-1500 reactor, nuclear safety are discussed. Problems and threats arousing from the closure of Ignalina NPP and possibilities of nuclear power after reactors shutdown are disputed. Papers on heating and district heating networks, heat and mass transfer, renewable energy sources and protection of biosphere are presented

[en] The dependencies of changes of hydraulic loss coefficient of the fast acting motor valve in respect of relative valve opening (closure) rate obtained by RELAP5 code and two separate CFD codes are compared. The series of thermal-hydraulic calculations of maximum design-basis accident initiated by full break of main circulation pump pressure header or pipeline using these three types of valve characteristics were performed. The impact of the fast acting motor valves characteristics on the loss of coolant accident in the RBMK-1500 reactor evolution process parameters is demonstrated. (author)

[en] An overview of Lithuania nuclear sector is presented. Status of art and main problems are presented. Lithuania operates the biggest in the world RBMK reactor according to the rules and standards accepted by lAEA and international nuclear society. Lithuanian regulatory body VATESI has issued operational licence for Ignalina NPP unit 2 on the basis of safety analysis report and independent review of it. (author)

[en] Radium is strong gamma ray emitter. In this article the measurements of doses rates distribution and evaluation of activity are presented. (author)

[en] The finite element model of fast acting hydraulic motor valve was developed and analysed, using two separate computational fluid dynamic codes in parallel. The dependencies of changes of hydraulic loss coefficient in respect of relative valve opening (closure) rate are presented. The results obtained can be used for verification of thermohydraulic codes for analysis of accident and transient processes in nuclear reactors. (author)

[en] Paper analyses development of power system in the Baltic region in the time period until 2025 while calculating period covers time span until 2025. Analysis is based on mathematical modeling of various scenarios seeking to minimize total system cost and keeping emissions into atmosphere below required constrains. (author)

[en] Calculations using the 3-D Monte Carlo code Monte Carlo N-Particle version C were performed in order to find the proper material of beam-shaping assembly for boron neutron capture therapy applications. (author)

[en] Modifications were applied to RELAP5/MOD3.3 code and the condensation implosion was modeled. Modeled results fairly meet the experimental data. Modifications still cannot be implemented for versatile use, as the conditions need to be fit to each case of condensation implosion separately. (author)

[en] An assessment methodology and results of neutron activation of RBMK-1500 type nuclear reactor fuel channels is presented in this work. The model for evaluation of neutron activation was developed based on conservative assumptions and the assessment of radioactivity levels in the E125 type alloy (fuel channels) was performed using the computer code ORIGEN-S. The results of neutron activation estimation show that from the radiological point of view the most important radionuclides induced during neutron activation in reactor fuel channels are: 3H, 14C, 41Ca, 55Fe, 60Co, 59Ni, 63Ni, 93Zr, 93mNb, 94Nb. (author)

[en] Two reactivity coefficients i. e. void and power were investigated. Both reactivity coefficients are of high safety relevance for RBMK type reactors. The uncertainty of the reactivity effects investigated was quantified in terms of statistical tolerance limits. The sensitivity analysis provided a ranking of the uncertain input parameters with respect to their contribution to the uncertainty of the reactivity effects. (author)