Investigation of Downward Facing CHF with Water-Based Nanofluids for IVR

In-Vessel Retention (IVR) through External Reactor Vessel Cooling is a severe accident management measure that is power limiting to the Westinghouse AP1000 due to critical heat flux (CHF) at the outer surface of the vessel. Increasing CHF by altering the coolant would increase safety margin at curre...

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Main Authors: Dewitt, Gregory Lee, Buongiorno, Jacopo, McKrell, Thomas J., Hu, Lin-Wen, Park, R. J.
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Format: Article
Language:en_US
Published: American Nuclear Society 2014
Online Access:http://hdl.handle.net/1721.1/87109
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author Dewitt, Gregory Lee
Buongiorno, Jacopo
McKrell, Thomas J.
Hu, Lin-Wen
Park, R. J.
author2 Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
author_facet Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Dewitt, Gregory Lee
Buongiorno, Jacopo
McKrell, Thomas J.
Hu, Lin-Wen
Park, R. J.
author_sort Dewitt, Gregory Lee
collection MIT
description In-Vessel Retention (IVR) through External Reactor Vessel Cooling is a severe accident management measure that is power limiting to the Westinghouse AP1000 due to critical heat flux (CHF) at the outer surface of the vessel. Increasing CHF by altering the coolant would increase safety margin at current design power or allow for higher power. Modification to current design would not require significant changes to the containment and systems.
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spelling mit-1721.1/871092022-10-02T06:48:16Z Investigation of Downward Facing CHF with Water-Based Nanofluids for IVR Dewitt, Gregory Lee Buongiorno, Jacopo McKrell, Thomas J. Hu, Lin-Wen Park, R. J. Massachusetts Institute of Technology. Department of Nuclear Science and Engineering MIT Nuclear Reactor Laboratory Dewitt, Gregory Lee Buongiorno, Jacopo McKrell, Thomas J. Hu, Lin-Wen In-Vessel Retention (IVR) through External Reactor Vessel Cooling is a severe accident management measure that is power limiting to the Westinghouse AP1000 due to critical heat flux (CHF) at the outer surface of the vessel. Increasing CHF by altering the coolant would increase safety margin at current design power or allow for higher power. Modification to current design would not require significant changes to the containment and systems. 2014-05-22T19:32:47Z 2014-05-22T19:32:47Z 2011-06 Article http://purl.org/eprint/type/ConferencePaper http://hdl.handle.net/1721.1/87109 DeWitt, G., R. J. Park, J. Buongiorno, T. McKrell, L. W. Hu. "Investigation of Downward Facing CHF with Water-Based Nanofluids for IVR." American Nuclear Society 2011 Annual Meeting, June 26-30, 2011, Hollywood, Florida. en_US http://www.ans.org/meetings/m_75 Proceedings of the American Nuclear Society 2011 Annual Meeting Creative Commons Attribution-Noncommercial-Share Alike http://creativecommons.org/licenses/by-nc-sa/4.0/ application/pdf American Nuclear Society Prof. Buongiorno via Chris Sherratt
spellingShingle Dewitt, Gregory Lee
Buongiorno, Jacopo
McKrell, Thomas J.
Hu, Lin-Wen
Park, R. J.
Investigation of Downward Facing CHF with Water-Based Nanofluids for IVR
title Investigation of Downward Facing CHF with Water-Based Nanofluids for IVR
title_full Investigation of Downward Facing CHF with Water-Based Nanofluids for IVR
title_fullStr Investigation of Downward Facing CHF with Water-Based Nanofluids for IVR
title_full_unstemmed Investigation of Downward Facing CHF with Water-Based Nanofluids for IVR
title_short Investigation of Downward Facing CHF with Water-Based Nanofluids for IVR
title_sort investigation of downward facing chf with water based nanofluids for ivr
url http://hdl.handle.net/1721.1/87109
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