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Title: Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY Short Term Station Black Out

Authors:
; ; ; ; ; ;
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1411837
Resource Type:
Journal Article: Publisher's Accepted Manuscript
Journal Name:
Nuclear Engineering and Design
Additional Journal Information:
Journal Volume: 313; Journal Issue: C; Related Information: CHORUS Timestamp: 2017-12-07 13:39:25; Journal ID: ISSN 0029-5493
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Wang, Jun, Mccabe, Mckinleigh, Wu, Lei, Dong, Xiaomeng, Wang, Xianmao, Haskin, Troy Christopher, and Corradini, Michael L. Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY Short Term Station Black Out. Netherlands: N. p., 2017. Web. doi:10.1016/j.nucengdes.2017.01.002.
Wang, Jun, Mccabe, Mckinleigh, Wu, Lei, Dong, Xiaomeng, Wang, Xianmao, Haskin, Troy Christopher, & Corradini, Michael L. Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY Short Term Station Black Out. Netherlands. doi:10.1016/j.nucengdes.2017.01.002.
Wang, Jun, Mccabe, Mckinleigh, Wu, Lei, Dong, Xiaomeng, Wang, Xianmao, Haskin, Troy Christopher, and Corradini, Michael L. Wed . "Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY Short Term Station Black Out". Netherlands. doi:10.1016/j.nucengdes.2017.01.002.
@article{osti_1411837,
title = {Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY Short Term Station Black Out},
author = {Wang, Jun and Mccabe, Mckinleigh and Wu, Lei and Dong, Xiaomeng and Wang, Xianmao and Haskin, Troy Christopher and Corradini, Michael L.},
abstractNote = {},
doi = {10.1016/j.nucengdes.2017.01.002},
journal = {Nuclear Engineering and Design},
number = C,
volume = 313,
place = {Netherlands},
year = {Wed Mar 01 00:00:00 EST 2017},
month = {Wed Mar 01 00:00:00 EST 2017}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record at 10.1016/j.nucengdes.2017.01.002

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  • A postulated, low-pressure, short term station blackout severe accident has been analyzed using the MELCOR code for the Grand Gulf nuclear power plant. Different versions have been used with three different models of the plant. This paper presents results of the effects of different plant models and versions of MELCOR on the calculated results and to present the best-estimating timing of events for this transient.
  • This study compares results obtained with two U.S. Nuclear Regulatory Commission (NRC)-sponsored codes, MELCOR version 1.8.3 (1.8PQ) and SCDAP/RELAP5 Mod3.1 release C, for the same transient - a low-pressure, short-term station blackout accident at the Browns Ferry nuclear plant. This work is part of MELCOR assessment activities to compare core damage progression calculations of MELCOR against SCDAP/RELAP5 since the two codes model core damage progression very differently.
  • A fully qualified, best-estimate MELCOR deck has been prepared for the Grand Gulf Nuclear Station and has been run using MELCOR 1.8.3 (1.8 PN) for a low-pressure, short-term, station blackout severe accident. The same severe accident sequence has been run with the same MELCOR version for the same plant using the deck prepared during the NUREG-1150 study. A third run was also completed with the best-estimate deck but without the Lower Plenum Debris Bed (BH) Package to model the lower plenum. The results from the three runs have been compared, and substantial differences have been found. The timing of importantmore » events is shorter, and the calculated source terms are in most cases larger for the NUREG-1150 deck results. However, some of the source terms calculated by the NUREG-1150 deck are not conservative when compared to the best-estimate deck results. These results identified some deficiencies in the NUREG-1150 model of the Grand Gulf Nuclear Station. Injection recovery sequences have also been simulated by injecting water into the vessel after core relocation started. This marks the first use of the new BH Package of MELCOR to investigate the effects of water addition to a lower plenum debris bed. The calculated results indicate that vessel failure can be prevented by injecting water at a sufficiently early stage. No pressure spikes in the vessel were predicted during the water injection. The MELCOR code has proven to be a useful tool for severe accident management strategies.« less
  • The MELCOR code, developed by Sandia National Laboratories, is a fully integrated, relatively fast-running code that models the progression of severe accidents in commercial light water nuclear power plants (NPPs).A specific station blackout (SBO) accident for Kuosheng (BWR-6) NPP is simulated using the MELCOR 1.8.4 code. The MELCOR input deck for Kuosheng NPP is established based on Kuosheng NPP design data and the MELCOR users' guides. The initial steady-state conditions are generated with a developed self-initialization algorithm. The main severe accident phenomena and the fission product release fractions associated with the SBO accident were simulated. The predicted results are plausiblemore » and as expected in light of current understanding of severe accident phenomena. The uncertainty of this analysis is briefly discussed. The important features of the MELCOR 1.8.4 are described. The estimated results provide useful information for the probabilistic risk assessment (PRA) of Kuosheng NPP. This tool will be applied to the PRA, the severe accident analysis, and the severe accident management study of Kuosheng NPP in the near future.« less