BPSD code upgrade for solving the nuclear kinetics problem

Seleznyov, Evgenij Fyodorovich; Belov, A. A.; Belousov, V.I.; Chernova, I. S.

doi:10.26583/npe.2018.4.10

Cited by 7 publications

(3 citation statements)

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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

“…В 2019 г. была начата доработка кода ЕВКЛИД/V1 для возможности расчетов ре жимов работы реакторной установки с учетом выгорания активной зоны и перегруз ки ТВС в рамках микрокампаний на базе актуальной версии программы BPSD [6] (код аттестован в 2021 г. [7]).…”

Section: реализация расчета микрокампаний в коде евклид/V1unclassified

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

Belov

Bereznev

Blokhina

et al. 2022

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Section: описание интегрального кода евклид/V1unclassified

Section: реализация расчета микрокампаний в коде евклид/V1unclassified

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

Belov

Bereznev

Blokhina

et al. 2022

YadEn

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“…In 2019, work began on modifying the EUCLID/V1 code to enable computations of reactor operating modes, taking into account core burnup and fuel assembly loading, as part of micro-campaigns based on the current version of the BPSD program (Seleznyov et al 2018a) (the code was certified in 2021 (Attestation Certificate 2021). For this aim, the following modifications were made in the code:…”

Section: Micro-campaign Computations In the Euclid/v1 Codementioning

confidence: 99%

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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