skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Loss-of-coolant accident mitigation for the Advanced Neutron Source Reactor

Abstract

A RELAP5 Advanced Neutron Source Reactor system model has been developed for the conceptual design safety analysis. Three major regions modeled are the core, the heat exchanger loops, and letdown/pressurizing system. The model has been used to examine design alternatives for mitigation of loss-of-coolant accident (LOCA) transients. The safety margins to the flow excursion limit and critical heat flux are presented. The results show that the core can survive an instantaneous double-ended guillotine of the core outlet piping break (610 mm-diameter) provided a cavitating venturi is employed. RELAP5 calculations were also used to determine the effects of using a non-instantaneous break opening times. Both break opening time and break formation characteristics were included in these parametric calculations. Accumulator optimization studies were also performed which suggest that an optimum accumulator bubble size exists which improves system performance under some break scenarios.

Authors:
; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10183925
Report Number(s):
CONF-930830-33
ON: DE94018966; TRN: 94:018995
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: National conference and exposition on heat transfer,Atlanta, GA (United States),8-11 Aug 1993; Other Information: PBD: [1994]
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; EXPERIMENTAL REACTORS; LOSS OF COOLANT; DESIGN BASIS ACCIDENTS; SAFETY ANALYSIS; 220900; 220600; REACTOR SAFETY; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS

Citation Formats

Chen, N C.J., Wendel, M W, and Yoder, Jr, G L. Loss-of-coolant accident mitigation for the Advanced Neutron Source Reactor. United States: N. p., 1994. Web.
Chen, N C.J., Wendel, M W, & Yoder, Jr, G L. Loss-of-coolant accident mitigation for the Advanced Neutron Source Reactor. United States.
Chen, N C.J., Wendel, M W, and Yoder, Jr, G L. Thu . "Loss-of-coolant accident mitigation for the Advanced Neutron Source Reactor". United States. https://www.osti.gov/servlets/purl/10183925.
@article{osti_10183925,
title = {Loss-of-coolant accident mitigation for the Advanced Neutron Source Reactor},
author = {Chen, N C.J. and Wendel, M W and Yoder, Jr, G L},
abstractNote = {A RELAP5 Advanced Neutron Source Reactor system model has been developed for the conceptual design safety analysis. Three major regions modeled are the core, the heat exchanger loops, and letdown/pressurizing system. The model has been used to examine design alternatives for mitigation of loss-of-coolant accident (LOCA) transients. The safety margins to the flow excursion limit and critical heat flux are presented. The results show that the core can survive an instantaneous double-ended guillotine of the core outlet piping break (610 mm-diameter) provided a cavitating venturi is employed. RELAP5 calculations were also used to determine the effects of using a non-instantaneous break opening times. Both break opening time and break formation characteristics were included in these parametric calculations. Accumulator optimization studies were also performed which suggest that an optimum accumulator bubble size exists which improves system performance under some break scenarios.},
doi = {},
url = {https://www.osti.gov/biblio/10183925}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1994},
month = {9}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: