The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part II: Model assessment and application

Tran, Chi Thanh; Dinh, Truc-Nam

doi:10.1016/j.pnucene.2009.06.001

Cited by 34 publications

(7 citation statements)

References 10 publications

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“…The simulation results show that for a debris bed (melt pool) less than 0.7 m thick formed in the lower plenum, the CRGT cooling at the nominal water flow rate is sufficient for removing the decay heat and thus is likely adequate to ensure the integrity of the reactor pressure vessel. With a thicker debris bed, the vessel wall is predicted to fail in the section close to the uppermost region of debris bed (melt pool) [76]. The simulation with a metal layer shows that in a stratified melt pool (0.2 m metal layer in 1.0 m total thickness) the focusing effect is ameliorated, thanks to the CRGT cooling.…”

Section: In-vessel Melt/debris Coolabilitymentioning

confidence: 97%

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In-Vessel Core Degradation

2012

Nuclear Safety in Light Water Reactors

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Section: In-vessel Melt/debris Coolabilitymentioning

confidence: 97%

“…An extensive study on the efficiency of CRGT cooling as a SAM measure has been conducted at the Royal Institute of Technology [75] [76] [77] [78]. Figure 2.33 shows a conceptual configuration of corium pool in a BWR lower head with CRGT cooling and top flooding.…”

Section: In-vessel Melt/debris Coolabilitymentioning

confidence: 99%

In-Vessel Core Degradation

2012

Nuclear Safety in Light Water Reactors

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“…Wang, Mingjun et al performed three-dimensional CFD simulations with three types of internal structures in the lower plenum, and the influence of different internal structures on the flow characteristics in the lower plenum was achieved and analyzed [7]. TRAN C T developed the ECM capability to accurately predict energy splitting and heat flux profiles in volumetrically heated liquid pools of different geometries over a range of conditions related to accident progression, examined and benchmarked against both experimental data and CFD results [8]. Maatki, Chemseddine et al numerically performed the entropy generation of double diffusive natural convection in a three-dimensional differentially heated enclosure [9].…”

Section: Introductionmentioning

confidence: 99%

CFD Calculation of Natural Convection Heat Transmission in a Three-Dimensional Pool with Hemispherical Lower Head

Mao,

Chen,

Wang

et al. 2024

Energies

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The integrity of a pressure vessel (PRV) is affected by the decay heat of the molten pool in the lower head, so it is very important to study the natural convection heat transmission in the lower head. Scholars from all over the world have carried out a lot of experimental studies and calculations to determine the convection mechanism and heat transmission characteristics of the molten pool. Most of them were based on the empirical formula of convective heat transmission on the wall of a hemispherical molten pool based on two-dimensional slice experiments and simulation calculations. In this study, FLUENT 2021R1 software was used to simulate the three-dimensional convective heat transmission process of the hemispherical molten pool, and the temperature, velocity and wall heat transmission coefficients of the flow field were analyzed. The results were in good agreement with experimental data from UCLA (University of California, Los Angeles). Through research on the heat transmission of the lower head, the results showed that in the region where the wall angle was θ between approximately 72 and 90 degrees, heat transmission coefficients had larger fluctuations, and a more reasonable empirical relation was proposed. Comparing between the simulation results of CFD and the two-dimensional empirical formula, it was found that the latter one was smaller under the same θ angle condition. Finally, the convection phenomena of different external temperatures were simulated, and the main factors affecting the flow field by temperature were analyzed.

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“…Right from the first, the severe accident codes have greatly contributed to analysis of IVR strategy. Since the analytical methods [7,8] and numerical methods [9,10,11] require initial bounding conditions which mostly provided by severe accident analysis codes such as RELAP5/SCDAP and MELCOR code, in order to evaluate the thermal response of lower head wall under heat load from molten pool. The RELAP5/SCDAP was used to provide bounding conditions including mass of molten debris and its components, temperature, and decay heat deposited in molten debris in an extensive series of severe accident calculations for AP1000 [4] and APR1400 [5].…”

Section: Introductionmentioning

confidence: 99%

Analysis of in-vessel accident progression in VVER1000 NPP during SBO accident with external reactor vessel cooling method

Manh¹,

Van²,

Tran³

2020

Nucl. Sci. and Tech.

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In this study, the MELCOR v1.8.6 code was utilized to perform an analysis of the in-vessel accident progression in VVER1000 reactor during the Station Black-Out (SBO) accident with and without external reactor vessel cooling (ERVC) strategy. The analysis presented the predictions of the main phenomena during the accident such as failure of fuel cladding, collapse of lower core support plate, relocation of core debris to lower plenum and mass of debris components in lower plenum, and provided comparisons between two cases in term of main parameters such as integrity time of reactor and structure components of molten pool. These parameters are very important inputs for further research on the application of external vessel cooling strategy for VVER1000 reactor.

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The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part II: Model assessment and application

Cited by 34 publications

References 10 publications

In-Vessel Core Degradation

In-Vessel Core Degradation

CFD Calculation of Natural Convection Heat Transmission in a Three-Dimensional Pool with Hemispherical Lower Head

Analysis of in-vessel accident progression in VVER1000 NPP during SBO accident with external reactor vessel cooling method

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