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Title: Advanced liquid-metal reactor IHX protection from a severe sodium/water reaction event

Abstract

The US program for development of an advanced liquid-metal reactor (ALMR) is proceeding into a significant new phase of focused design development utilizing a national team under US Department of Energy sponsorship. A project goal is to demonstrate by full-scale testing the safety features of one reactor module, thereby providing the technological basis for design certification by the US Nuclear Regulatory Commission. The reference design for the 1395-MW(electric) plant utilizes three 465-MW(electric) power blocks. Each power block, representing the basic building block in the ALMR concept, consists of three identical 471-MW(thermal) reactor modules located below grade, each with its own steam generator (SG) system, which are headered into a common turbine generator. One of the innovative features of the ALMR is the manner in which the SG and associated interfacing systems have been configured to provide assured protection of the intermediate heat exchanger (IHX) tubes from a worst-case SG tube leak and resulting sodium/water reaction event. For this event, it is assumed that, despite the very low probability of occurrence, all the tubes in the SG fail and the steam-side isolation and blowdown system fails to function and terminate the event. This paper describes a design approach to ensure protectionmore » against this highly unlikely event.« less

Authors:
 [1];  [2]; ;
  1. Westinghouse AES, Madison, PA (USA)
  2. Babcock and Wilcox Co., Barberton, OH (USA)
Publication Date:
OSTI Identifier:
6125165
Report Number(s):
CONF-900608-
Journal ID: ISSN 0003-018X; CODEN: TANSA; TRN: 91-008324
Resource Type:
Conference
Journal Name:
Transactions of the American Nuclear Society; (USA)
Additional Journal Information:
Journal Volume: 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; Journal ID: ISSN 0003-018X
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LMFBR TYPE REACTORS; REACTOR SAFETY; STEAM GENERATORS; MOLTEN METAL-WATER REACTIONS; ENGINEERED SAFETY SYSTEMS; FEEDWATER; HEAT EXCHANGERS; MODULAR STRUCTURES; PRIMARY COOLANT CIRCUITS; RESEARCH PROGRAMS; SODIUM; STEAM; US DOE; USA; ALKALI METALS; BOILERS; BREEDER REACTORS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HYDROGEN COMPOUNDS; LIQUID METAL COOLED REACTORS; METALS; NATIONAL ORGANIZATIONS; NORTH AMERICA; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; US ORGANIZATIONS; VAPOR GENERATORS; WATER; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding

Citation Formats

Lowrie, R R, Kakarala, C, Boardman, C E, and Hui, M M. Advanced liquid-metal reactor IHX protection from a severe sodium/water reaction event. United States: N. p., 1990. Web.
Lowrie, R R, Kakarala, C, Boardman, C E, & Hui, M M. Advanced liquid-metal reactor IHX protection from a severe sodium/water reaction event. United States.
Lowrie, R R, Kakarala, C, Boardman, C E, and Hui, M M. Fri . "Advanced liquid-metal reactor IHX protection from a severe sodium/water reaction event". United States.
@article{osti_6125165,
title = {Advanced liquid-metal reactor IHX protection from a severe sodium/water reaction event},
author = {Lowrie, R R and Kakarala, C and Boardman, C E and Hui, M M},
abstractNote = {The US program for development of an advanced liquid-metal reactor (ALMR) is proceeding into a significant new phase of focused design development utilizing a national team under US Department of Energy sponsorship. A project goal is to demonstrate by full-scale testing the safety features of one reactor module, thereby providing the technological basis for design certification by the US Nuclear Regulatory Commission. The reference design for the 1395-MW(electric) plant utilizes three 465-MW(electric) power blocks. Each power block, representing the basic building block in the ALMR concept, consists of three identical 471-MW(thermal) reactor modules located below grade, each with its own steam generator (SG) system, which are headered into a common turbine generator. One of the innovative features of the ALMR is the manner in which the SG and associated interfacing systems have been configured to provide assured protection of the intermediate heat exchanger (IHX) tubes from a worst-case SG tube leak and resulting sodium/water reaction event. For this event, it is assumed that, despite the very low probability of occurrence, all the tubes in the SG fail and the steam-side isolation and blowdown system fails to function and terminate the event. This paper describes a design approach to ensure protection against this highly unlikely event.},
doi = {},
url = {https://www.osti.gov/biblio/6125165}, journal = {Transactions of the American Nuclear Society; (USA)},
issn = {0003-018X},
number = ,
volume = 61,
place = {United States},
year = {1990},
month = {6}
}

Conference:
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