SAMEX: A severe accident management support expert

Park, Sooyong; Ahn, Kwang-Il

doi:10.1016/j.anucene.2010.04.014

Cited by 16 publications

(11 citation statements)

References 2 publications

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“…Since ATLAS requires preparation with selected scenarios, an instant application due to this paper's result would be uncertainty analyses and database-driven simulations such as in [22]. However, an underlying idea of ATLAS is that the local errors essentially depend only on local system's states for a simulator, and thereby applying ATLAS to scenarios other than ones used in the preparation is possible.…”

Section: Discussionmentioning

confidence: 99%

“…This is particularly important, since researchers and analysts frequently encounter the need to run simulations in a short amount of time by changing parameter values like this case (i.e. in sensitivity analysis, uncertainty analysis, and accident management support systems [22]). Preparing ATLAS for more general scenarios would require a well-organized sampling of the relevant scenarios' data, which we do not discuss in this paper, leaving it as future work.…”

Section: A Problem Descriptionmentioning

confidence: 99%

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An Adaptive Time-Stepping Scheme with Local Convergence Verification Using Support Vector Machines

Kawaguchi¹,

Ishikawa²,

Maruyama³

2014

IJET

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Abstract-An adaptive time-stepping scheme in accordance with the local convergence of computation often involves computationally expensive procedures. As a result, many computer simulators have avoided utilizing such an adaptive scheme, while its advantages are well recognized; the scheme not only efficiently allocates computational resources, but also makes the results of the computation more reliable. In this paper, we propose a fast adaptive time-stepping scheme, ATLAS (Adaptive Time-step Learning and Adjusting Scheme), which approximates such an expensive yet beneficial scheme by using support vector machines (SVMs). We demonstrate that ATLAS performs quite favorably when compared with computations without it. ATLAS can incorporate existing solvers and other fast but unreliable adaptive schemes to meet the different criteria required in various applications.Index Terms-Adaptive time step control, machine learning, ordinary differential equations, severe accident analysis.

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Section: Discussionmentioning

confidence: 99%

Section: A Problem Descriptionmentioning

confidence: 99%

An Adaptive Time-Stepping Scheme with Local Convergence Verification Using Support Vector Machines

Kawaguchi¹,

Ishikawa²,

Maruyama³

2014

IJET

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“…Therefore, such tools can be used for planning measures to mitigate core damage and source term estimation. MARS (Iguchi et al, 1999;Raines et al, 1993), ADAM (Khatib-Rahbar et al, 2001;Zavisca et al, 2002), CAMS (Øwre, 2001;Vayssier et al, 2006) and SAMEX (Park and Ahn, 2010) are fast running tools for accident management support.…”

Section: Accident Management Support Tools In Nuclear Power Plantsmentioning

confidence: 97%

“…MELCOR and MAAP are the most interesting severe accident codes for Predictor design because of their simplified modeling and fast running capability (Iguchi et al, 1999;Jeong et al, 2002;Park and Ahn, 2010;Raines et al, 1993;Vayssier et al, 2006). MAAP (Henry and Landgren, 2003) has a predetermined nodalization and specific versions for PWR, BWR and WWER type NPPs.…”

Section: Severe Accident Codesmentioning

confidence: 98%

Accident management support tools in nuclear power plants: A post-Fukushima review

Saghafi

Ghofrani

2016

Progress in Nuclear Energy

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“…In addition, many countries have used MELCOR for the regulation of LWR [14]. Particularly, the Korean regulatory body has utilized MELCOR for monitoring and judgement of SAs [15,16]. Thus, in this study, MELCOR version 2.1 was used to investigate effectiveness and adverse effects of the ICRV.…”

Section: Melcor Codementioning

confidence: 99%

A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident

Kim

Choi

Jeon

et al. 2018

Science and Technology of Nuclear Installations

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During a hypothesized severe accident, a containment building is designed to act as a final barrier to prevent release of fission products to the environment in nuclear power plants. However, in a bypass scenario of steam generator tube rupture (SGTR), radioactive nuclides can be released to environment even if the containment is not ruptured. Thus, thorough mitigation strategies are needed to prevent such unfiltered release of the radioactive nuclides during SGTR accidents. To mitigate the consequence of the SGTR accident, this study was conducted to devise a conceptual approach of installing In-Containment Relief Valve (ICRV) from steam generator (SG) to the free space in the containment building and it was simulated by MELCOR code for numerical analysis. Simulation results show that the radioactive nuclides were not released to the environment in the ICRV case. However, the containment pressure increased more than the base case, which is a disadvantage of the ICRV. To minimize the negative effects of the ICRV, the ICRV linked to Reactor Drain Tank (RDT) and cavity flooding was performed. Because the overpressurization of containment is due to heat of ex-vessel corium, only cavity flooding was effective for depressurization. The conceptual design of the ICRV is effective in mitigating the SGTR accident.

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SAMEX: A severe accident management support expert

Cited by 16 publications

References 2 publications

An Adaptive Time-Stepping Scheme with Local Convergence Verification Using Support Vector Machines

An Adaptive Time-Stepping Scheme with Local Convergence Verification Using Support Vector Machines

Accident management support tools in nuclear power plants: A post-Fukushima review

A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident

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