The Development and Application of SCDAP-3D©

Coryell, E.W.; Harvego, Edwin A.; Siefken, L.J.

doi:10.1115/icone10-22638

Cited by 2 publications

(1 citation statement)

References 2 publications

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“…For the thermal-hydraulic nodalization, the reactor vessel is discretized into radial rings and axial levels. Recent applications of a 3-D version of SCDAP/RELAP5 have been presented in which the rings are further divided into segments (Coryell et al, 2002). Core structures in both codes are placed within the thermal-hydraulic control volumes.…”

Section: Core Modelsmentioning

confidence: 99%

Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes

Vierow¹,

Liao²,

Johnson³

et al. 2004

Nuclear Engineering and Design

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Based on knowledge obtained from experimental programs, considerable progress has been made in severe accident code development. The three leading severe accident codes used in the U.S., MELCOR, MAAP4 and SCDAP/RELAP5, are compared herein as part of an evaluation of the relative state of severe accident modeling in each of the codes.The MELCOR code is evolving from a probabilistic risk assessment tool to a best-estimate severe accident system analysis code. Some advantages that MELCOR has are the capability to evaluate containment behavior and the source term to the environment, and the great modeling flexibility that the control volume approach and control functions afford. The MAAP4 code was developed to perform fast-running full simulations of severe accidents. Due in part to the simplified form of the conservation equations and the coarser discretization of the reactor systems, MAAP4 has calculation times far shorter than those of the other codes while producing credible results. The SCDAP/RELAP5 code contains more mechanistic physics models than the other codes for both severe accident and thermal-hydraulic phenomena and has undergone extensive validation against plant and experimental data.The codes' overall attributes, relevant physics models and calculation results are compared herein. A hypothetical TMLB' scenario (station blackout with no recovery of auxiliary feedwater) at a 4-loop pressurized water reactor (PWR) was calculated by all three codes. Detailed plots showed that, despite considerable differences in the codes themselves, the calculation results of the codes are very similar in terms of thermal-hydraulic and core degradation response. There are minor discrepancies in various timings of phenomena, which are within the uncertainties of the code numerical computation and the physics models. The thermal challenge to the primary loop radionuclide barrier, such as the steam generator tube heat structures, is also compared among the three codes.

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Section: Core Modelsmentioning

confidence: 99%

Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes

Vierow¹,

Liao²,

Johnson³

et al. 2004

Nuclear Engineering and Design

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Accident progression analysis P-300

Germain

Akers

2016

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This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability of responsibility for any third party's use, or the results of such use, or any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.

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The Development and Application of SCDAP-3D©

Abstract: The SCDAP-3D

Cited by 2 publications

References 2 publications

Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes

Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes

Accident progression analysis P-300

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