The «CORNER» neutronics calculation code

Bereznev, V; Seleznyov, Evgenij Fyodorovich; Asatryan, D. S.

doi:10.26583/npe.2015.1.15

Cited by 4 publications

(1 citation statement)

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“…Нейтронно физический расчет в интегральном коде ЕВКЛИД/V1 осуществляется на базе модуля DN3D, реа лизующего диффузионную (одноточечная, семиточечная, гибридная расчетные схе мы) и кинетическую опции (на базе метода дискретных ординат). Диффузионная и кинетическая опции базируются на использовании кодов DOLCE VITA [4] и CORNER [5] соответственно, автономные версии которых аттестованы в 2021 г.…”

Section: описание интегрального кода евклид/V1unclassified

Simulating a Lead&Cooled Reactor Campaign Using the EUCLID/V1 Code

Belov

Bereznev

Blokhina

et al. 2022

YadEn

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Section: описание интегрального кода евклид/V1unclassified

Simulating a Lead&Cooled Reactor Campaign Using the EUCLID/V1 Code

Belov

Bereznev

Blokhina

et al. 2022

YadEn

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Codes of new generation for safety justification of power units with a closed nuclear fuel cycle developed for the “PRORYV” project

Bolshov¹,

Strizhov²,

Mosunova³

2020

NUCET

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The article describes the status of development of codes of new generation for the “PRORYV” Project by the end of 2019: twenty-five commercial-grade software products to justify design solutions and safety of power units with fast neutron reactors and liquid metal coolant (sodium and lead) in a closed nuclear fuel cycle. The developed system of codes is multi-physical and multi-scale that allows performing both calculations of the whole installations and high precision calculations of their individual elements. The developed codes offer unique features. Twelve developed codes have already been certified by Rostechnadzor, and six more have been submitted for certification. In addition to creating the software products, a large-scale work is being carried out to conduct experimental studies for code validation that meet modern requirements imposed by the codes: unique measurement techniques have been created; experimental data on flow characteristics of heavy liquid metal coolant (HLMC) in a fuel assembly simulator have been obtained, as well as of “gas-HLMC” interphase interaction after inert gas injection in HLMC and characteristics of heat exchange between the inert gas and HLMC. The results are already used for validation of system and CFD codes used in the “PRORYV” Project.

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Simulating a lead-cooled reactor campaign using the EUCLID/V1 code

Белов¹,

Bereznev²,

Blokhina³

et al. 2022

NUCET

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The paper presents the results of the development of the EUCLID/V1 integrated dynamic code designed to analyze and justify the safety of fast neutron reactor facilities with a liquid-metal coolant, in terms of simulating the reactor campaign. The relevance of this study lies in the need to simulate the behavior of the core at any time during the campaign. It lets us to obtain a full dataset for subsequent simulations of the reactor dynamic conditions (including transient states or accidents). The authors have developed a fuel archive to store calculated data in HDF5 format, created a computational model editor to generate input data in the fuel archive format, and also provided an example of computing the campaign of a lead-cooled fast reactor for three core design models shown in this paper. The main array of fuel assemblies was simulated as a single unit in the first model, as three units in the second model, and in the third every single assembly was unique. In addition, the authors have shown changes in the total masses of actinides in the core, revealed that the different core models have an insignificant effect on the evolution of the total masses of actinides, and given the fuel assembly burnup values for the three core models. For the third model, the largest difference between the minimum and maximum burnup values was obtained with an almost identical average over the fuel assemblies. The reactivity margin over time for the three core models was presented. It was shown that the values and behavior of the reactivity margin during the three micro-campaigns are almost equal. From the fourth to the sixth cycle, the reactivity margin value for the third core model was lower than for the first and the second ones. Finally, the authors conclude that it is desirable to evaluate the behavior of the reactivity margin for lead-cooled fast reactor campaigns based on the detailed model of the core.

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The «CORNER» neutronics calculation code

Cited by 4 publications

References 0 publications

Simulating a Lead&Cooled Reactor Campaign Using the EUCLID/V1 Code

Simulating a Lead&Cooled Reactor Campaign Using the EUCLID/V1 Code

Codes of new generation for safety justification of power units with a closed nuclear fuel cycle developed for the “PRORYV” project

Simulating a lead-cooled reactor campaign using the EUCLID/V1 code

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The «CORNER» neutronics calculation code

Cited by 4 publications

References 0 publications

Simulating a Lead&Cooled Reactor Campaign Using the EUCLID/V1 Code

Simulating a Lead&Cooled Reactor Campaign Using the EUCLID/V1 Code

Codes of new generation for safety justification of power units with a closed nuclear fuel cycle developed for the “PRORYV” project

﻿Simulating a lead-cooled reactor campaign using the EUCLID/V1 code

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Product

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Simulating a lead-cooled reactor campaign using the EUCLID/V1 code