Main outcomes from the IVR code benchmark performed in the European IVMR project

Carénini, L.; Fichot, F.; Bakouta, N.; Филиппов, А. С.; Tellier, R. Le; Viot, Louis; Мельников, И. В.; Pandazis, P.

doi:10.1016/j.anucene.2020.107612

Cited by 21 publications

(7 citation statements)

References 22 publications

(18 reference statements)

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“…This identification would require performing more sensitivity studies with the codes and a more precise evaluation of the existing uncertainties in material properties. Such work was initiated in the scope of the benchmark exercise on IVR performed between ASTEC, ATHLET-CD, HEFEST-SOCRAT, HEFEST-URAN, MAAP EDF proprietary version and PROCOR (Carénini et al 2019). The predominant effect of metal properties compared to those of the oxide was confirmed.…”

Section: Ranking Of Parameters Impacting the Risks Of Excessive Heat ...mentioning

confidence: 96%

Elaboration of a Phenomena Identification Ranking Table (PIRT) for the modelling of In-Vessel Retention

Fichot¹,

Carénini²,

Bakouta

et al. 2020

Annals of Nuclear Energy

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Section: Ranking Of Parameters Impacting the Risks Of Excessive Heat ...mentioning

confidence: 96%

Elaboration of a Phenomena Identification Ranking Table (PIRT) for the modelling of In-Vessel Retention

Fichot¹,

Carénini²,

Bakouta

et al. 2020

Annals of Nuclear Energy

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“…Анализ расчетных оценок скорости окисления показывает, что наиболее чувствительным параметром выражения (9) является теплопроводность оксидной корки, неопределенность значения которой не превышает 25%. Приведенные в [37] результаты бенчмарка IVR-кодов свидетельствуют, что разброс значений исходных параметров моделей может превышать 50%. Это может приводить к вариации расчетных оценок до 70% от средней величины.…”

Section: определение параметров модели и обсуждение результатовunclassified

“…Это может приводить к вариации расчетных оценок до 70% от средней величины. Таким образом, предложенная расчетная зависимость может быть интегрирована в существующие расчетные коды без существенного увеличения неопределенности расчетных оценок [37].…”

Section: определение параметров модели и обсуждение результатовunclassified

Моделирование Окисления Расплава Активной Зоны Ядерного Реактора При Наличии Оксидной Корки На Поверхности Расплава

Khabenskii¹,

Альмяшев²,

Granovskii³

et al. 2021

Журнал Технической Физики

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At a severe accident of nuclear power plants with light-water reactors, the most effective way to localize the forming melt (corium) is to keep it in the cooled reactor vessel, the integrity of which depends on the value of heat flux from the melt to the reactor vessel. In this case, one of the critical processes is the melt oxidation by a water steam or a steam-air mixture. It process can lead to a significant increase in the thermal load on the reactor vessel due to a heat of exothermic reactions of oxidation of reducing agents, which presents in the melt, a thickness decreasing of the metallic part of the molten pool, and a hydrogen release. All of these factors strictly depends on the rate of oxidation. When considering the conditions of melt oxidation, it taken into account that for the accepted scenarios of a severe accident, the most realistic situation is the presence of a solid-phase oxide layer (oxidic crust) on the melt surface. Under these conditions, a dependence for calculating the rate of core melt oxidation based on the diffusion model proposed and its validation by using the obtained experimental data performed.

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“…It is secondly due to the uncertainty of physical models used in integral codes for severe accident analysis. The calculation results of integral codes (including ASTEC, ATHLET-CD, and MAAP_EDF) for the minimum vessel thickness show a large variability (about ±80%) (Carénini et al, 2019). The significant discrepancy leads to a great uncertainty in the reasonable assessment of IVR-ERVC effectiveness.…”

Section: Introductionmentioning

confidence: 99%

Research on Optimized Design of In-Vessel Retention–External Reactor Vessel Cooling Strategy and Negative Effect Assessment

Chen

Zhan

et al. 2022

Front. Energy Res.

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Due to large uncertainty, the effectiveness of in-vessel retention (IVR) with external reactor vessel cooling (ERVC) for high-power reactors cannot be fully demonstrated during the transient process. To optimize the current IVR-ERVC strategy, the concept of IVR-ERVC with in-vessel injection (IVI) is studied. Two feasible IVI designs are proposed: 1) using the passive IVR water tank to implement simultaneous water injection in-vessel and ex-vessel and 2) using the passive severe accident dedicated in-vessel injection tanks (SADITs) to implement water injection in-vessel. The research on the feasibility and effectiveness of IVI is performed, and the corresponding negative effects are analyzed. The calculation results by using MIDAC show that the two proposed IVI concepts can greatly delay the accident progression in the core and reduce the decay heat peak of the molten pool in the lower head, thereby improving the effectiveness of the current IVR-ERVC strategy. And the negative effects are within acceptable ranges.

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Main outcomes from the IVR code benchmark performed in the European IVMR project

Cited by 21 publications

References 22 publications

Elaboration of a Phenomena Identification Ranking Table (PIRT) for the modelling of In-Vessel Retention

Elaboration of a Phenomena Identification Ranking Table (PIRT) for the modelling of In-Vessel Retention

Моделирование Окисления Расплава Активной Зоны Ядерного Реактора При Наличии Оксидной Корки На Поверхности Расплава

Research on Optimized Design of In-Vessel Retention–External Reactor Vessel Cooling Strategy and Negative Effect Assessment

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