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

Андрианов, А. А.; Osipova, Tatiana Andreevna; Andrianova, Olga Nikolaevna; Utyanskaya, Tatyana Vladimirovna

doi:10.26583/npe.2018.3.09

Cited by 2 publications

(2 citation statements)

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“…Actualized and updated data on the BFS-66, -64 and -80 assemblies were used as the basis for building detailed precision neutronic models with a description of the BFS heterogeneous structure and experimental devices for Monte Carlo based codes, including MCU-BR, MCNP, MMK-RF, and MMK-ROKOKO (Gomin et al 2000, Andrianova et al 2016, Zherdev et al 2018) with BNAB-RF and MDBBR50 neutron data, and the ROS-FOND evaluated neutron data library (Andrianova et al 2018), which allow calculating key neutronic characteristics measured at the BFS-66, -64 and -80 assemblies, and being important in terms of estimating the uncertainty of the power density in the steel reflector of a lead cooled fast reactor plant.…”

Section: Calculation Resultsmentioning

confidence: 99%

Precision neutronic calculations of experiments on the neutron transmission through the reflector layers at the BFS critical facilities for expanding the verification database to justify lead cooled fast reactor designs

Andrianova¹,

Teplukhina²,

Zherdev³

et al. 2020

NUCET

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The paper presents the results of the efforts concerned with expanding the verification database and estimating the calculation uncertainty of the power density in the steel reflector of lead cooled fast reactor designs based on experiments performed in different years at the BFS critical assemblies by analyzing and revising earlier calculation and experimental studies on the transmission of neutrons through the steel reflector layers. The discussion includes experiments at the BFS-66 critical assembly to model neutron and photon fluxes in the reactor core shielding compositions, as well as experiments at the BFS-64 and BFS-80-2 critical assemblies to model the transmission of neutrons and gamma quanta through the reflector layers of various materials. The information provided in earlier materials with the descriptions of the above experiments has been analyzed and expanded through respective data required to prepare precision calculation models for Monte-Carlo neutronic codes. Precision neutronic models have been developed based on actualized and updated data with a detailed description of the BFS heterogeneous structure and experimental devices, and test calculations have been carried out to confirm their efficiency. The calculations of key neutronic characteristics measured at the BFS-66, -64 and -80-2 assemblies were performed using codes based on the Monte Carlo method (MCU-BR, MCNP, MMK-RF, MMK-ROKOKO) with BNAB-RF and MDBBR50 neutron data and the ROSFOND evaluated neutron data library. The developed precision calculation neutronic models of the experiments discussed can be used to justify lead cooled fast reactor designs, to verify neutronic codes and neutron data, and to evaluate the associated uncertainties.

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Section: Calculation Resultsmentioning

confidence: 99%

Precision neutronic calculations of experiments on the neutron transmission through the reflector layers at the BFS critical facilities for expanding the verification database to justify lead cooled fast reactor designs

Andrianova¹,

Teplukhina²,

Zherdev³

et al. 2020

NUCET

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“…The following assumptions were made to model the nuclear power capacity growth for the scenario analysis: 35 GW in 2030, 55 GW in 2050, and 103 GW in 2100 (Andrianov et (Andrianov et al 2018). The cost of the NFC services was taken from (Alekseev et al 2016).…”

Section: Initial Data and Assumptionsmentioning

confidence: 99%

Multi-criteria evaluation and ranking of potential scenarios for the development of Russian two-component nuclear energy system with thermal and sodium-cooled fast reactors

Usanov¹,

Kvyatkovskiy²,

Андрианов³

2021

NUCET

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The paper presents the results from a multi-criteria comparative evaluation of potential deployment scenarios for Russian nuclear power with thermal and sodium-cooled fast reactors in a closed nuclear fuel cycle (the so-called two-component nuclear energy system). The comparison and the ranking were performed taking into account the recommendations and using the IAEA/INPRO software tools for comparative evaluation of nuclear energy systems, including tools for sensitivity/uncertainty analysis with respect to weighting factors. Ten potential Russian nuclear power deployment scenarios with different shares of thermal and sodium-cooled fast reactors were considered, including options involving the use of MOX fuel in VVER reactors. Eight key indicators were used, estimated as of 2100 and structured into a three-level objectives tree. The comparative evaluation and the ranking were carried out based on the multi-attribute value theory. The model for assessing the key indicators was developed using the IAEA/INPRO MESSAGE-NES energy system planning software tool. The information base for the study was formed by publications of experts from JSC SSC RF-IPPE, NRC Kurchatov Institute and NRNU MEPhI. The presented results show that it is possible to enhance significantly the sustainability of the Russian nuclear energy system, when considering multiple performance indicators, through the intensive deployment of sodium-cooled fast reactors and the transition to a closed nuclear fuel cycle. Tasks have been outlined for the follow-up studies to make it possible to obtain more rigorous conclusions regarding the preferred options for the evolution of a two-component nuclear energy system.

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

Cited by 2 publications

References 0 publications

Precision neutronic calculations of experiments on the neutron transmission through the reflector layers at the BFS critical facilities for expanding the verification database to justify lead cooled fast reactor designs

Precision neutronic calculations of experiments on the neutron transmission through the reflector layers at the BFS critical facilities for expanding the verification database to justify lead cooled fast reactor designs

Multi-criteria evaluation and ranking of potential scenarios for the development of Russian two-component nuclear energy system with thermal and sodium-cooled fast reactors

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