Overview of experimental programs on core melt progression and fission product release behaviour

Lewis, Brent J.; Dickson, R.; Iglesias, F.C.; Ducros, G.; Kudo, Tamotsu

doi:10.1016/j.jnucmat.2008.07.005

Cited by 77 publications

(31 citation statements)

References 62 publications

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“…The melting point of this eutectic is lower than uranium oxide. Figure 3.3 shows high temperature phenomena of the fuel relating to the core-melt progression [2,3]. Some radioactive materials in the fuel soluble in UO 2 were released following heating and melting of the fuel.…”

Section: Model 1: Release From Fuel With Known/assumed Inventorymentioning

confidence: 99%

“…Modular Accident Analysis Program (MAAP) was developed [2,3] by U.S. industries while MELCOR was developed by the United States Nuclear Regulatory Commission (US NRC) [5].…”

Section: Model 2: Codes For Severe Accident Progression Analysismentioning

confidence: 99%

“…Using these data, amounts of radionuclides and chemical elements for FP and MA at one day after the scram were calculated using the ORIGEN code. 2 Figures 3.10 and 3.11 show the inventories of radionuclide and chemical elements in 1F1 at one day after the scram, respectively.…”

Section: Approach Based On Radionuclide Release Analysis: Modelmentioning

confidence: 99%

“…The following nuclides were found to be significant based on the produced amount and half-life: 239 2 We made a rough estimate of inventory data on July 2011 with use of ORIGEN 2.2, assuming conditions about core and operation of the reactor, which might be considered similar to those of 1F1. Fig.…”

Section: Approach Based On Radionuclide Release Analysis: Modelmentioning

confidence: 99%

See 3 more Smart Citations

Analysis of Radioactive Release from the Fukushima Daiichi Nuclear Power Station

Tanaka

Kado

2014

Reflections on the Fukushima Daiichi Nuclear Accident

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Basic schemes and databases necessary to assess the radioactive release in severe accidents at nuclear power plants are presented. The approaches include one based on the physical and chemical properties of the core fuel, and another based on the radiation monitor. Trials of the rough evaluation for the severe accident at Fukushima Daiichi nuclear power station are made using both approaches without relying on specialized computer simulations for educational purposes, even though the exact values will be less reliable. The results were compared with the official statements by the authorities for both cases, and confirmed to be nevertheless fairly consistent with each other. This fact implies that these "manual calculation-based" approaches are practically useful, especially for accidents where detailed simulation results have not yet come out, or are still unavailable or ambiguous. Background of the database, such as atmospheric diffusion, flash boiling, and radiological equivalence including dose factor, are described in the appendixes.

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Section: Model 1: Release From Fuel With Known/assumed Inventorymentioning

confidence: 99%

“…Modular Accident Analysis Program (MAAP) was developed [2,3] by U.S. industries while MELCOR was developed by the United States Nuclear Regulatory Commission (US NRC) [5].…”

Section: Model 2: Codes For Severe Accident Progression Analysismentioning

confidence: 99%

Section: Approach Based On Radionuclide Release Analysis: Modelmentioning

confidence: 99%

Section: Approach Based On Radionuclide Release Analysis: Modelmentioning

confidence: 99%

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Analysis of Radioactive Release from the Fukushima Daiichi Nuclear Power Station

Tanaka

Kado

2014

Reflections on the Fukushima Daiichi Nuclear Accident

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“…3. LOFT is a PWR model with a rated power of 50 MWth, including all systems and components needed to simulate a severely damaged core assembly and to determine the fission product release and transport to the piping system [Lewis et al, 2008]. The LOFT-FP project, completed in 1985[IRSN-200783, 2007 This test has provided very interesting data on core degradation and fission product release and transport in a V-type LOCA sequence, under low system pressure, in a decay-heated bundle, and at a larger scale compared with other bundle in-reactor tests.…”

Section: Description Of Loft Lp-fp-2 Experimentsmentioning

confidence: 99%

A Bayesian ensemble of sensitivity measures for severe accident modeling

Hoseyni

Maio

Vagnoli

et al. 2015

Nuclear Engineering and Design

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In this work, a sensitivity analysis framework is presented to identify the relevant input variables of a severe accident code, based on an incremental Bayesian ensemble updating method. The proposed methodology entails: i) the propagation of the uncertainty in the input variables through the severe accident code; ii) the collection of bootstrap replicates of the input and output of limited number of simulations for building a set of Finite Mixture Models (FMMs) for approximating the probability density function (pdf) of the severe accident code output of the replicates; iii) for each FMM, the calculation of an ensemble of sensitivity measures (i.e., input saliency, Hellinger distance and Kullback-Leibler divergence) and the updating when a new piece of evidence arrives, by a Bayesian scheme, based on the Bradley-Terry model for ranking the most relevant input model variables. An application is given with respect to a limited number of simulations of a MELCOR severe accident model describing the fission products release in the LP-FP-2 experiment of the Loss Of Fluid Test (LOFT) facility, which is a scaled-down facility of a pressurized water reactor (PWR).

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Investigation of core meltdown phenomena and radioactive materials release in VVER‐1000/V446 nuclear reactor at severe accident condition due to LBLOCA along SBO

2019

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Overview of experimental programs on core melt progression and fission product release behaviour

Cited by 77 publications

References 62 publications

Analysis of Radioactive Release from the Fukushima Daiichi Nuclear Power Station

Analysis of Radioactive Release from the Fukushima Daiichi Nuclear Power Station

A Bayesian ensemble of sensitivity measures for severe accident modeling

Investigation of core meltdown phenomena and radioactive materials release in VVER‐1000/V446 nuclear reactor at severe accident condition due to LBLOCA along SBO

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