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Title: Final Project Report on Computational Modeling and Analysis of Air-Based NSTF

Abstract

The Reactor Cavity Cooling System (RCCS) is a passive safety concept under consideration for the overall safety strategy of advanced reactors such as the High Temperature Gas-Cooled Reactor (HTGR). The air-cooled RCCS uses natural convection to drive the flow of air from outside the power plant to remove decay heat during normal operation and accident scenarios. The Natural convection Shutdown heat removal Test Facility (NSTF) at Argonne National Laboratory (“Argonne”) is a ½ - scale model of the primary features of one conceptual air-cooled RCCS design. The NSTF program performs ex-vessel, passive heat removal experiments in support of Department of Energy Office of Nuclear Energy’s Advanced Reactor Technology (ART) program.

Authors:
 [1];  [1];  [1];  [1];  [1]
+ Show Author Affiliations
  1. Argonne National Lab. (ANL), Argonne, IL (United States)
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE), Reactor Fleet and Advanced Reactor Development. Nuclear Reactor Technologies; Advanced Reactor Technologies (ART)
OSTI Identifier:
1429403
Report Number(s):
ANL-ART-46
128752
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Hu, R., Kraus, A., Bucknor, M., Lv, Q., and Lisowski, D. Final Project Report on Computational Modeling and Analysis of Air-Based NSTF. United States: N. p., 2016. Web. doi:10.2172/1429403.
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Hu, R., Kraus, A., Bucknor, M., Lv, Q., & Lisowski, D. Final Project Report on Computational Modeling and Analysis of Air-Based NSTF. United States. https://doi.org/10.2172/1429403
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Hu, R., Kraus, A., Bucknor, M., Lv, Q., and Lisowski, D. 2016. "Final Project Report on Computational Modeling and Analysis of Air-Based NSTF". United States. https://doi.org/10.2172/1429403. https://www.osti.gov/servlets/purl/1429403.
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@article{osti_1429403,
title = {Final Project Report on Computational Modeling and Analysis of Air-Based NSTF},
author = {Hu, R. and Kraus, A. and Bucknor, M. and Lv, Q. and Lisowski, D.},
abstractNote = {The Reactor Cavity Cooling System (RCCS) is a passive safety concept under consideration for the overall safety strategy of advanced reactors such as the High Temperature Gas-Cooled Reactor (HTGR). The air-cooled RCCS uses natural convection to drive the flow of air from outside the power plant to remove decay heat during normal operation and accident scenarios. The Natural convection Shutdown heat removal Test Facility (NSTF) at Argonne National Laboratory (“Argonne”) is a ½ - scale model of the primary features of one conceptual air-cooled RCCS design. The NSTF program performs ex-vessel, passive heat removal experiments in support of Department of Energy Office of Nuclear Energy’s Advanced Reactor Technology (ART) program.},
doi = {10.2172/1429403},
url = {https://www.osti.gov/biblio/1429403}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {6}
}
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Technical Report:
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https://doi.org/10.2172/1429403
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