MELCOR Analysis of OSU Multi-Application Small Light Water Reactor (MASLWR) Experiment
Abstract
A multi-application small light water reactor (MASLWR) conceptual design was developed by Oregon State University (OSU) with emphasis on passive safety systems. The passive containment safety system employs condensation and natural circulation to achieve the necessary heat removal from the containment in case of postulated accidents. Containment condensation experiments at the MASLWR test facility at OSU are modeled and analyzed with MELCOR, a system-level reactor accident analysis computer code. The analysis assesses its ability to predict condensation heat transfer in the presence of noncondensable gas for accidents where high-energy steam is released into the containment. This work demonstrates MELCOR’s ability to predict the pressure-temperature response of the scaled containment. Our analysis indicates that the heat removal rates are underestimated in the experiment due to the limited locations of the thermocouples and applies corrections to these measurements by conducting integral energy analyses along with CFD simulation for confirmation. Furthermore, the corrected heat removal rate measurements and the MELCOR predictions on the heat removal rate from the containment show good agreement with the experimental data.
- Authors:
-
- Univ. of Wisconsin, Madison, WI (United States)
- Tsinghua Univ., Beijing (China)
- Oregon State Univ., Corvallis, OR (United States)
- Publication Date:
- Research Org.:
- Univ. of Wisconsin, Madison, WI (United States); Oregon State Univ., Corvallis, OR (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1372322
- Grant/Contract Number:
- NE0000663
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Technology
- Additional Journal Information:
- Journal Volume: 198; Journal Issue: 3; Journal ID: ISSN 0029-5450
- Publisher:
- Taylor & Francis - formerly American Nuclear Society (ANS)
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; condensation; multi-application small light water reactor; MELCOR
Citation Formats
Yoon, Dhongik S., Jo, HangJin, Fu, Wen, Wu, Qiao, and Corradini, Michael L. MELCOR Analysis of OSU Multi-Application Small Light Water Reactor (MASLWR) Experiment. United States: N. p., 2017.
Web. doi:10.1080/00295450.2017.1311119.
Yoon, Dhongik S., Jo, HangJin, Fu, Wen, Wu, Qiao, & Corradini, Michael L. MELCOR Analysis of OSU Multi-Application Small Light Water Reactor (MASLWR) Experiment. United States. https://doi.org/10.1080/00295450.2017.1311119
Yoon, Dhongik S., Jo, HangJin, Fu, Wen, Wu, Qiao, and Corradini, Michael L. Tue .
"MELCOR Analysis of OSU Multi-Application Small Light Water Reactor (MASLWR) Experiment". United States. https://doi.org/10.1080/00295450.2017.1311119. https://www.osti.gov/servlets/purl/1372322.
@article{osti_1372322,
title = {MELCOR Analysis of OSU Multi-Application Small Light Water Reactor (MASLWR) Experiment},
author = {Yoon, Dhongik S. and Jo, HangJin and Fu, Wen and Wu, Qiao and Corradini, Michael L},
abstractNote = {A multi-application small light water reactor (MASLWR) conceptual design was developed by Oregon State University (OSU) with emphasis on passive safety systems. The passive containment safety system employs condensation and natural circulation to achieve the necessary heat removal from the containment in case of postulated accidents. Containment condensation experiments at the MASLWR test facility at OSU are modeled and analyzed with MELCOR, a system-level reactor accident analysis computer code. The analysis assesses its ability to predict condensation heat transfer in the presence of noncondensable gas for accidents where high-energy steam is released into the containment. This work demonstrates MELCOR’s ability to predict the pressure-temperature response of the scaled containment. Our analysis indicates that the heat removal rates are underestimated in the experiment due to the limited locations of the thermocouples and applies corrections to these measurements by conducting integral energy analyses along with CFD simulation for confirmation. Furthermore, the corrected heat removal rate measurements and the MELCOR predictions on the heat removal rate from the containment show good agreement with the experimental data.},
doi = {10.1080/00295450.2017.1311119},
journal = {Nuclear Technology},
number = 3,
volume = 198,
place = {United States},
year = {2017},
month = {5}
}
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