Design of passive decay heat removal system for the lead cooled flexible conversion ratio fast reactor

Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007.

Bibliographic Details
Main Author: Whitman, Joshua (Joshua J.)
Other Authors: Neil E. Todreas.
Format: Thesis
Language:eng
Published: Massachusetts Institute of Technology 2008
Subjects:
Online Access:http://hdl.handle.net/1721.1/41690
_version_ 1811081682449596416
author Whitman, Joshua (Joshua J.)
author2 Neil E. Todreas.
author_facet Neil E. Todreas.
Whitman, Joshua (Joshua J.)
author_sort Whitman, Joshua (Joshua J.)
collection MIT
description Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007.
first_indexed 2024-09-23T11:50:49Z
format Thesis
id mit-1721.1/41690
institution Massachusetts Institute of Technology
language eng
last_indexed 2024-09-23T11:50:49Z
publishDate 2008
publisher Massachusetts Institute of Technology
record_format dspace
spelling mit-1721.1/416902019-04-11T03:33:02Z Design of passive decay heat removal system for the lead cooled flexible conversion ratio fast reactor Whitman, Joshua (Joshua J.) Neil E. Todreas. Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering. Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering. Nuclear Science and Engineering. Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007. Includes bibliographical references. The lead-cooled flexible conversion ratio fast reactor shows many benefits over other fast-reactor designs; however, the higher power rating and denser primary coolant present difficulties for the design of a passive decay heat removal system. In order to achieve passive cooling, enhancements are needed over current designs, such as the S-PRISM and ABR, which utilize passive cooling through the reactor vessel to atmospheric air. Enhancements such as axial fins, a perforated plate, and round indentations, or dimples, were considered as additions to the hot air riser to increase heat transfer. Other enhancements include a liquid metal bond between the reactor and guard vessels, and a dual-level design which introduces ambient temperature air halfway up the vessel wall. A code was written in Java to simulate these conditions, leading to a promising case using dimples on the guard vessel wall as the primary mode of heat transfer enhancement, and including the dual-level design. A conservative estimate of dimple performance indicates that during a passive decay heat removal shutdown, bulk primary coolant temperature will peak at 713 'C, giving a 12 OC margin to clad failure. Attempts were made to refine the uncertainty within the calculations using a computational fluid dynamics code, Fluent, but these ultimately were unsuccessful. Additional studies were conducted on the static stress imparted on the vessel, and the dynamic stress caused by a seismic event. The static stress was found to be within ASME code limits. Seismic analysis determined that a seismic isolation scheme would be necessary in order to prevent damage to the vessel during an earthquake. by Joshua Whitman. S.B. 2008-05-19T16:08:59Z 2008-05-19T16:08:59Z 2007 2007 Thesis http://hdl.handle.net/1721.1/41690 221272735 eng M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission. http://dspace.mit.edu/handle/1721.1/7582 78 p. application/pdf Massachusetts Institute of Technology
spellingShingle Nuclear Science and Engineering.
Whitman, Joshua (Joshua J.)
Design of passive decay heat removal system for the lead cooled flexible conversion ratio fast reactor
title Design of passive decay heat removal system for the lead cooled flexible conversion ratio fast reactor
title_full Design of passive decay heat removal system for the lead cooled flexible conversion ratio fast reactor
title_fullStr Design of passive decay heat removal system for the lead cooled flexible conversion ratio fast reactor
title_full_unstemmed Design of passive decay heat removal system for the lead cooled flexible conversion ratio fast reactor
title_short Design of passive decay heat removal system for the lead cooled flexible conversion ratio fast reactor
title_sort design of passive decay heat removal system for the lead cooled flexible conversion ratio fast reactor
topic Nuclear Science and Engineering.
url http://hdl.handle.net/1721.1/41690
work_keys_str_mv AT whitmanjoshuajoshuaj designofpassivedecayheatremovalsystemfortheleadcooledflexibleconversionratiofastreactor