Conceptual framework of a strategy for the development of nuclear power in Russia to 2100

Адамов, Е. О.; Dzhalavyan, A. V.; Lopatkin, A. V.; Molokanov, N. A.; Muravyov, E. V.; Orlov, V. V.; Kal’akin, S. G.; Rachkov, V. I.; Troyanov, V. M.; Avrorin, E. N.; Ivanov, V. B.; Aleksakhin, R. M.

doi:10.1007/s10512-012-9574-x

Cited by 50 publications

(17 citation statements)

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“…For this purpose, it is necessary to identify the characteristic structural features of the models of the discussed two-component NES options, estimate the uncertainties in the levelized generation costs (LGC) 1 and the NES structures caused by the uncertainty in the costs of NFC services and reactor technologies. The information base of the study consists of technical-economic data and scenario assumptions presented in the publications of experts from the NRC "Kurchatov Institute", JSC "SSC RF-IPPE", ITCP "Proryv", and JSC "NIKIET" (Ponomarev-Stepnoy 2016, Alekseev et al 2011, Alekseev et al 2012, Alekseev et al 2017, Adamov 2001, Adamov et al 2012, Adamov et al 2017, Muravyev 2014.…”

Section: Problem Statement and Initial Datamentioning

confidence: 99%

“…Currently, of all possible options for the national nuclear energy development, two alternatives are most actively discussed: they are denoted by the common term, i.e., two-component nuclear energy system (NES). It is assumed that such a system at different time horizons may contain in its composition both thermal and fast reactors coupled by a closed nuclear fuel cycle (NFC) (Ponomarev-Stepnoy 2016, Alekseev et al 2011, Alekseev et al 2012, Alekseev et al 2017, Adamov 2001, Adamov et al 2012, Adamov et al 2017, Muravyev 2014.…”

Section: Introductionmentioning

confidence: 99%

“…In the second option (hereinafter Option 2), thermal reactors will continue to use uranium oxide fuel as long as there are resources of natural uranium available at an affordable cost, and fast reactors (with or without fuel breeding) will use mixed nitride uranium-plutonium (MNUP) fuel, plutonium for which can be extracted from SNF of both thermal and fast reactors. The implementation of both centralized and on-site NFC is assumed to be possible under this option (Adamov 2001, Adamov et al 2012, Adamov et al 2017, Muravyev 2014.…”

Section: Introductionmentioning

confidence: 99%

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Optimization models of a two-component nuclear energy system with thermal and fast reactors in a closed nuclear fuel cycle

Андрианов¹,

Osipova

Andrianova

et al. 2019

NUCET

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The article presents a description and some illustrative results of the application of two optimization models for a two-component nuclear energy system consisting of thermal and fast reactors in a closed nuclear fuel cycle. These models correspond to two possible options of developing Russian nuclear energy system, which are discussed in the expert community: (1) thermal and fast reactors utilizing uranium and mixed oxide fuel, (2) thermal reactors utilizing uranium oxide fuel and fast reactors utilizing mixed nitride uranium-plutonium fuel. The optimization models elaborated using the IAEA MESSAGE energy planning tool make it possible not only to optimize the nuclear energy system structure according to the economic criterion, taking into account resource and infrastructural constraints, but also to be used as a basis for developing multi-objective, stochastic and robust optimization models of a two-component nuclear energy system. These models were elaborated in full compliance with the recommendations of the IAEA’s PESS and INPRO sections, regarding the specification of nuclear energy systems in MESSAGE. The study is based on publications of experts from NRC “Kurchatov Institute”, JSC “SSC RF-IPPE”, ITCP “Proryv”, JSC “NIKIET”. The presented results demonstrate the characteristic structural features of a two-component nuclear energy system for conservative assumptions in order to illustrate the capabilities of the developed optimization models. Consideration is also given to the economic feasibility of a technologically diversified nuclear energy structure providing the possibility of forming on its base a robust system in the future. It has been demonstrated that given the current uncertainties in the costs of nuclear fuel cycle services and reactor technologies, it is impossible at the moment to make a reasonable conclusion regarding the greatest attractiveness of a particular option in terms of the economic performance.

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Section: Problem Statement and Initial Datamentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Optimization models of a two-component nuclear energy system with thermal and fast reactors in a closed nuclear fuel cycle

Андрианов¹,

Osipova

Andrianova

et al. 2019

NUCET

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“…Contractual price for the European Pressurized Reactor in 2004 was $3000/kW, then to $5000/kW due to 4 years behind construction schedule [2]. Capital costs of building nuclear power plants VVER have increased considerably from $1000/kW in 2000 to exceed $3000/kW in Russia, besides, operating & maintaining costs and nuclear electricity costs have also increased [19]. What is more serious is that EU Member States with a large share of nuclear power often have high electricity price levels for both households and industry customers, revealed by the German Institute for Applied Ecology in 2008.…”

Section: Nuclear Power In the Futurementioning

confidence: 99%

Role of Nuclear Power in the Future: Cost and Public Acceptance

Wang¹

2016

Proceedings of the 2016 International Conference on Mechanics, Materials and Structural Engineering

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The Fukushima accident pushed nuclear energy into dark criticism. Five years after, Japan is still faltering in its response to phase out nuclear. Global generating electricity from nuclear has decreased. Unfortunately, capital costs for renewables continue to fall, but costs of nuclear power keep rising. In addition, nuclear waste storage and spent fuel management problems are still unsolved. What's the nuclear power future? It has been plagued by the high cost of construction for a long time and the uncertain public acceptance after the Fukushima, as well as other strong competitors from renewables and fossil shale-gas in the near future.

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confidence: 99%

Experimental Research on Thermophysical Processes for Safety Validation of new-Generation Vver

et al. 2014

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The strategy for the development of nuclear power presupposes the construction of thermal water-cooled reactors and fast reactors [1][2][3]. At present, water moderated and cooled power reactors are the foundation of our country's nuclear power. The organizations of the State Corporation Rosatom have developed designs for new-generation reactor setups -AES-2006 and VVER-TOI, which are the result of evolutionary development and improvement of operating water moderated and cooled power reactors, which proved their reliability in thousands of reactor-years of accident-free operation. VVER are characterized by elevated power, the best economic and operational performance as well as enhanced safety compared with currently operating reactors. The thermal power is increased by, for example, using fuel assemblies with a new design incorporating heat-exchange intensifiers. The safety of the new designs of NPP with VVER is enhanced by means of the principle of technological diversity, which consists in combining active and passive safety systems. The passive systems ensure shutdown and prolonged removal of residual heat in the presence of a sealed loop or a depressurized loop and do not require operator intervention or an external long-time power source.To secure the possibility of increasing the power and validating the serviceability of new passive safety systems for VVER, a large-scale program of thermophysical and experimental studies has been completed.Increasing the Power Density and Efficiency of the VVER Core. The new NPP designs with VVER presuppose an improved design of the core as a whole and the fuel assemblies in particular. One promising avenue for increasing the capacity of power-generating units and the efficiency of the fuel cycle is to use fuel assemblies with improved thermohydraulic characteristics, which is accomplished by using mixing or intensifying lattices to increase heat transfer. Acting on the coolant flow these setups decrease the nonuniformity of the heating of the coolant (enthalpy) in the transverse section of a fuel assembly. They also make it possible to increase the turbulence properties of the flow, which causes moisture to settle on the walls of the fuel elements and promotes the removal of a large quantity of heat.In order to validate the heat-engineering reliability of a VVER core with fuel assemblies with mixing lattices, it is necessary to determine the effect of their design on the hydrodynamics and mass-transfer processes in the core. Important problems are the choice of the arrangement of the fuel assemblies and optimization of the design of the mixing lattices, which must possess the optimal combination of parameters such as the hydraulic resistance, the intensity of mixing of the coolant and a safety margin to crisis of boiling. The main method for studying the hydrodynamics and mass transfer in reactor fuel assemblies is the experimental investigation of fuel-assembly models on thermohydraulic stands: SVD-2, STF, and the TRASSER setup [4]. The main characteristics of the tripl...

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Conceptual framework of a strategy for the development of nuclear power in Russia to 2100

Cited by 50 publications

References 2 publications

Optimization models of a two-component nuclear energy system with thermal and fast reactors in a closed nuclear fuel cycle

Optimization models of a two-component nuclear energy system with thermal and fast reactors in a closed nuclear fuel cycle

Role of Nuclear Power in the Future: Cost and Public Acceptance

Experimental Research on Thermophysical Processes for Safety Validation of new-Generation Vver

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