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Title: System Analysis for Decay Heat Removal in Lead-Bismuth-Cooled Natural-Circulation Reactors

Abstract

Decay heat removal analyses for lead-bismuth-cooled natural-circulation reactors are described in this paper. A combined multidimensional plant dynamics code (MSG-COPD) has been developed to conduct the system analysis for the natural-circulation reactors. For the preliminary study, transient analysis has been performed for a 300-MW(thermal) lead-bismuth-cooled reactor designed by Argonne National Laboratory. In addition, decay heat removal characteristics of a 400-MW(electric) lead-bismuth-cooled natural-circulation reactor designed by the Japan Nuclear Cycle Development Institute (JNC) has been evaluated by using MSG-COPD. The primary reactor auxiliary cooling system (PRACS) is prepared for the JNC concept to get sufficient heat removal capacity. During 2000 s after the transient, the outlet temperature shows increasing tendency up to the maximum temperature of 430 deg. C because the buoyancy force in a primary circulation path is temporarily reduced. However, the natural circulation is recovered by the PRACS system, and the outlet temperature decreases successfully.

Authors:
 [1];  [1];  [2]
  1. Japan Nuclear Cycle Development Institute (Japan)
  2. Nuclear Energy System, Inc. (Japan)
Publication Date:
OSTI Identifier:
20837840
Resource Type:
Journal Article
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 145; Journal Issue: 3; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 0029-5450
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; AFTER-HEAT REMOVAL; BISMUTH; COOLING SYSTEMS; HEAT; LEAD; NATURAL CONVECTION; SYSTEMS ANALYSIS; TRANSIENTS

Citation Formats

Sakai, Takaaki, Enuma, Yasuhiro, and Iwasaki, Takashi. System Analysis for Decay Heat Removal in Lead-Bismuth-Cooled Natural-Circulation Reactors. United States: N. p., 2004. Web.
Sakai, Takaaki, Enuma, Yasuhiro, & Iwasaki, Takashi. System Analysis for Decay Heat Removal in Lead-Bismuth-Cooled Natural-Circulation Reactors. United States.
Sakai, Takaaki, Enuma, Yasuhiro, and Iwasaki, Takashi. 2004. "System Analysis for Decay Heat Removal in Lead-Bismuth-Cooled Natural-Circulation Reactors". United States.
@article{osti_20837840,
title = {System Analysis for Decay Heat Removal in Lead-Bismuth-Cooled Natural-Circulation Reactors},
author = {Sakai, Takaaki and Enuma, Yasuhiro and Iwasaki, Takashi},
abstractNote = {Decay heat removal analyses for lead-bismuth-cooled natural-circulation reactors are described in this paper. A combined multidimensional plant dynamics code (MSG-COPD) has been developed to conduct the system analysis for the natural-circulation reactors. For the preliminary study, transient analysis has been performed for a 300-MW(thermal) lead-bismuth-cooled reactor designed by Argonne National Laboratory. In addition, decay heat removal characteristics of a 400-MW(electric) lead-bismuth-cooled natural-circulation reactor designed by the Japan Nuclear Cycle Development Institute (JNC) has been evaluated by using MSG-COPD. The primary reactor auxiliary cooling system (PRACS) is prepared for the JNC concept to get sufficient heat removal capacity. During 2000 s after the transient, the outlet temperature shows increasing tendency up to the maximum temperature of 430 deg. C because the buoyancy force in a primary circulation path is temporarily reduced. However, the natural circulation is recovered by the PRACS system, and the outlet temperature decreases successfully.},
doi = {},
url = {https://www.osti.gov/biblio/20837840}, journal = {Nuclear Technology},
issn = {0029-5450},
number = 3,
volume = 145,
place = {United States},
year = {Mon Mar 15 00:00:00 EST 2004},
month = {Mon Mar 15 00:00:00 EST 2004}
}