Simulation of the ICE P1 test for a validation of COCOSYS and ASTEC codes

Povilaitis, Mantas; Kačegavičius, Tomas; Urbonavičius, E.

doi:10.1016/j.fusengdes.2015.03.021

Cited by 4 publications

(4 citation statements)

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“…The mathematical model of heat/mass transfer in the containment (Zaitsev 2005, Levchenko 2007) is a system of ordinary differential equations for conservation of momentum, energy and gas mixture components recorded for each selected control volume. This approach (i.e., modeling in lumped parameters) has become a frequent practice (Gauntt et al 2001, Murata 1997, Povilaitis et al 2015. In view of the significant effect of compressibility on the gas flow characteristics, instead of the momentum-conservation equation, dependences obtained for the adiabatic gas flow from pressure vessels are used.…”

Section: Calculation Methodsmentioning

confidence: 99%

“…The pressure in the left branch at the "0 m" elevation is equal to Р 0 + 40r 0 g. The pressure in the right branch at the "0 m" elevation will be greater, since the branch height-average gas density due to its compressibility in calculated Boxes 4, 3 and 2 is greater than r 0 , i.e., this nodalization scheme (if the Boltzmann density distribution throughout the box height is ignored) leads to the appearance of a non-zero pressure drop, causing the gas flow. Figures 3 and 4 show the results of numerical calculations of the considered closed loop with parameters close to the actual values of modern NPP containments (Table 2); the calculations were based on two mathematical models (one of height invariable dencity gas inside the box and the other of the SIMCO code, taking into account the gas compressibility (Povilaitis et al 2015)).…”

Section: Figure 1 Difference Between the Analytical And Numerical Somentioning

confidence: 99%

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The SIMCO containment code applied to modeling hydrogen distribution in containments of nuclear power facilities

Dorovskikh

Dorokhovich

Zajtsev

et al. 2018

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Citation: Dorovskikh VI, Dorokhovich SL, Zaytsev AA, Levchenko VA, Leonov IN (2018) The SIMCO containment code applied to modeling hydrogen distribution in containments of nuclear power facilities. Nuclear Energy and Technology 4(4): 279-285. AbstractThe article gives a general description of the SIMCO calculation code designed to simulate thermohydraulic and physico-chemical processes in containments of nuclear power facilities. The authors present a calculation technique based on a physico-mathematical model in lumped parameters. As a numerical solution method, the modified semi-implicit SIMPLER procedure is used. The code was examined using analytical and qualitative tests. A comparison of the numerical and analytical solutions showed good agreement. The code was verified using the experimental data obtained at the NUPEC installation (Japan). Based on the results of testing and verification, it was concluded that, in general, physico-mathematical code models adequately describe the processes of heat/mass transfer in the containment. Therefore, this SIMCO code version can be used to analyze the totality of thermophysical and physico-chemical processes in nuclear power facilities with containments, including the transfer of hydrogen/steam/air mixtures. SIMCO code general descriptionModernization of existing and development of new nuclear power plants meeting the increased requirements for reliability, safety and economical efficiency make it necessary to improve the calculation methods for reactors, heat exchange equipment as well as safety and accident localization systems. The containment is the fourth, final safety barrier to the spread of radioactive products to the environment. It is designed in accordance with regulatory documents, and heat/mass transfer processes in the containment during loss-of-coolant accidents (LOCA) are complex spatial in nature: they are characterized by numerous thermal, physical and chemical phenomena that determine the safety system effectiveness and reliability. For this reason, research processes in the containment

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Section: Calculation Methodsmentioning

confidence: 99%

Section: Figure 1 Difference Between the Analytical And Numerical Somentioning

confidence: 99%

The SIMCO containment code applied to modeling hydrogen distribution in containments of nuclear power facilities

Dorovskikh

Dorokhovich

Zajtsev

et al. 2018

YadEn

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“…The program COCOSYS, a lumped-parameter code, is being developed by the Gesellschaft für Anlagen-und Reaktorsicherheit (GRS) gGmbH, Germany, for the simulation of all relevant processes and plant states during severe accidents in containment of light water reactors. And this code is widely used in nuclear engineering [8,9]. The characteristic feature of lumped-parameter approach is that mass and energy are transferred between control volumes by junctions, according to momentum equation solution for each junction.…”

Section: Introductionmentioning

confidence: 99%

Assessment of Prediction Capabilities of COCOSYS and CFX Code for Simplified Containment

Zhu

Zhang

2016

Science and Technology of Nuclear Installations

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The acceptable accuracy for simulation of severe accident scenarios in containments of nuclear power plants is required to investigate the consequences of severe accidents and effectiveness of potential counter measures. For this purpose, the actual capability of CFX tool and COCOSYS code is assessed in prototypical geometries for simplified physical process-plume (due to a heat source) under adiabatic and convection boundary condition, respectively. Results of the comparison under adiabatic boundary condition show that good agreement is obtained among the analytical solution, COCOSYS prediction, and CFX prediction for zone temperature. The general trend of the temperature distribution along the vertical direction predicted by COCOSYS agrees with the CFX prediction except in dome, and this phenomenon is predicted well by CFX and failed to be reproduced by COCOSYS. Both COCOSYS and CFX indicate that there is no temperature stratification inside dome. CFX prediction shows that temperature stratification area occurs beneath the dome and away from the heat source. Temperature stratification area under adiabatic boundary condition is bigger than that under convection boundary condition. The results indicate that the average temperature inside containment predicted with COCOSYS model is overestimated under adiabatic boundary condition, while it is underestimated under convection boundary condition compared to CFX prediction.

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“…Skaitiniame modelyje daroma prielaida, kad ITER struktūrinių ir funkcinių medžiagų bandiniai buvo apšvitinti dideliais 14 MeV neutronų srautais (O-I)LTIS lokalizacijose. Šioje pozicijoje neutronų srautas yra didžiausias (iki 1020 n/m 2 , palyginti su sumine 1,7 • 10 21 neutronų išeiga), kaip ir dislokacijų kiekis, tenkantis atomui (10 -5 dpa). Bandinių aktyvumas ir dozės galios skaičiavimai po neutronų apšvitos buvo atlikti naudojant FISPACT-2010 programų paketą su EAF-2010 duomenų biblio teka.…”

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Branduolių sintezės tyrimai Lietuvos energetikos institute

Ušpuras¹,

Rimkevičius²,

Urbonavičius³

et al. 2016

energetika

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Kol buvo eksploatuojama Ignalinos AE, daugelis Lietuvos energetikos instituto (LEI) Branduolinių įrenginių saugos laboratorijos (BĮSL) mokslinių tyrimų buvo nukreipta branduolinių elektrinių saugos klausimams spręsti. Nuo 2006 m. LEI įsitraukė į mokslinius tyrimus, susijusius su branduolių sintezės tematika. Branduolių sintezė – tai procesas, kurio metu susijungia du lengvi branduoliai, pavyzdžiui, vandenilio izotopai deuteris ir tritis, sudarydami naują helio branduolį, o šio proceso metu išsiskiria milžiniškas energijos kiekis. Toks procesas vyksta ir žvaigždėse, o pasaulio mokslininkai sprendžia, kaip jį būtų galima suvaldyti ir pritaikyti Žemėje. Jei 2006 m. LEI vykdė tik nedidelį projektą, susijusį su vienu iš ITER reaktoriaus saugos aspektų, tai vėliau LEI BĮSL mokslininkai plėtė savo veiklos apimtis ir įsitraukė į naujas tyrimų sritis: neutronų pernašos procesų tyrimai, įrangos patikimumo tyrimai, įvairių konstrukcijų struktūrinio vientisumo tyrimai, t. t. Jau 2013 m. kartu su kitais Europos mokslinių tyrimų centrais LEI BĮSL dalyvavo rengiant kelrodį, kaip iki 2050 m. pasiekti, kad energija būtų gaminama ir branduolių sintezės įrenginiuose. Šis kelrodis tapo pagrindu parengti programos „Horizontas 2020“ EUROfusion projektą, kurio koordinatorius yra Vokietijos mokslinių tyrimų centras, įsikūręs Makso Planko Plazmos fizikos institute (Max-Planck Institut für Plasmaphysik). Tai pirmasis ir didžiausias ne tik finansiniu indėliu, bet ir ambicingumu Europos Sąjungos mokslinių tyrimų ir inovacijų programos projektas. Šiame straipsnyje trumpai apžvelgiama kiekviena iš tematikų, kuriose LEI BĮSL vykdė ir vykdo tyrimus nuo 2006 m. Straipsnio pabaigoje pateikiamas LEI mokslininkų paskelbtų pagrindinių publikacijų branduolių sintezės tematika sąrašas.

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Simulation of the ICE P1 test for a validation of COCOSYS and ASTEC codes

Cited by 4 publications

References 9 publications

The SIMCO containment code applied to modeling hydrogen distribution in containments of nuclear power facilities

The SIMCO containment code applied to modeling hydrogen distribution in containments of nuclear power facilities

Assessment of Prediction Capabilities of COCOSYS and CFX Code for Simplified Containment

Branduolių sintezės tyrimai Lietuvos energetikos institute

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