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Information × Registration Number 0216U000911, 0112U003597 , R & D reports Title Development of measures to enhance nuclear, radiation and environmental safety of the "shelter" and the new safe confinement popup.stage_title Head Krasnov Viktor Oleksandrovich, Registration Date 16-03-2016 Organization Institute for Safety Problems of Nuclear Power Plants popup.description2 The model of the basic processes that result in the southeastern part of the room 305/2 in the active phase of the accident could be formed Jans and output streams of lava-like fuel containing materials (LTSM). Obtained and verified temperature and time parameters of the basic processes in the flow "blast" lavoutvorennya version of the script. Consolidated material and energy balance model of the formation and structure rozmnozhuyuschohosya Jans environment in the area of ??penetration of the base plate reactor pit, then under-reactor plate (PP). Established that concrete temperature drop is not PE follows the drop in the residual heat (GR) fuel, and the total heat exceeds (100-150 W / ton uranium) GR by a forced separation Jans, subcriticality which is outside the emergency value. Stable condition Jans provided constant presence of water entering the Shelter from rain and condensation. Effects that lead to the opposite of criticism and samopidtrymuvannoyi chain reaction (CPR) with severe consequences may include: degradation of structures rozmnozhuyuschohosya environment, growth temperature and dehydration. The resulting calculation model qualitatively reproduces the dynamics of the emergence and development of CPR Jans. Veryfycation model based on the dynamics of CPR at critical re-registered in 1990. Qualitative assessment of the effectiveness of preventive suppression of critical parameters based on homogeneous and heterogeneous concentration distribution of neutron-absorbing materials (NPM) in the volume of material models Jans. A technical decision to exclude risks of CPR acceptable to the OC after the construction of the New Safe Confinement (NSC). The analysis of the factors leading to the occurrence of re-criticality during beyond design basis accidents (PAD) at the plant. Recommendations for prevention of repeated / re-criticality during operations to minimize the effects of PAD at the plant. It is concluded that the increase in temperature and dehydration of fuel clusters hidden masses due to the construction of a new safe confinement can lead to re-criticality and samopidtrymuvannoyi chain reaction of consequences related serious nuclear incident. The results can be used to develop measures to ensure nuclear safety of the "Shelter" and limit the effects of PAD on existing and planned nuclear power plants. Product Description popup.authors popup.nrat_date 2020-04-02 Close