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Title: Thermal hydraulics analysis of the Advanced High Temperature Reactor

Abstract

The Advanced High Temperature Reactor (AHTR) is a liquid salt-cooled nuclear reactor design concept, featuring low-pressure molten fluoride salt coolant, a carbon composite fuel form with embedded coated particle fuel, passively triggered negative reactivity insertion mechanisms, and fully passive decay heat rejection. This article describes an AHTR system model developed using the Nuclear Regulatory Commission (NRC) thermal hydraulic transient code TRAC/RELAP Advanced Computational Engine (TRACE). The TRACE model includes all of the primary components: the core, downcomer, hot legs, cold legs, pumps, direct reactor auxiliary cooling system (DRACS), the primary heat exchangers (PHXs), etc. The TRACE model was used to help define and size systems such as the DRACS and the PHX. A loss of flow transient was also simulated to evaluate the performance of the reactor during an anticipated transient event. Some initial recommendations for modifying system component designs are also discussed. Finally, the TRACE model will be used as the basis for developing more detailed designs and ultimately will be used to perform transient safety analysis for the reactor.

Authors:
 [1];  [2];  [2];  [2]
  1. Univ. of Massachusetts, Lowell, MA (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1348313
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Journal Article
Journal Name:
Nuclear Engineering and Design
Additional Journal Information:
Journal Volume: 294; Journal Issue: C; Journal ID: ISSN 0029-5493
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats

Wang, Dean, Yoder, Graydon L., Pointer, David W., and Holcomb, David E. Thermal hydraulics analysis of the Advanced High Temperature Reactor. United States: N. p., 2015. Web. doi:10.1016/j.nucengdes.2015.08.017.
Wang, Dean, Yoder, Graydon L., Pointer, David W., & Holcomb, David E. Thermal hydraulics analysis of the Advanced High Temperature Reactor. United States. doi:10.1016/j.nucengdes.2015.08.017.
Wang, Dean, Yoder, Graydon L., Pointer, David W., and Holcomb, David E. Tue . "Thermal hydraulics analysis of the Advanced High Temperature Reactor". United States. doi:10.1016/j.nucengdes.2015.08.017.
@article{osti_1348313,
title = {Thermal hydraulics analysis of the Advanced High Temperature Reactor},
author = {Wang, Dean and Yoder, Graydon L. and Pointer, David W. and Holcomb, David E.},
abstractNote = {The Advanced High Temperature Reactor (AHTR) is a liquid salt-cooled nuclear reactor design concept, featuring low-pressure molten fluoride salt coolant, a carbon composite fuel form with embedded coated particle fuel, passively triggered negative reactivity insertion mechanisms, and fully passive decay heat rejection. This article describes an AHTR system model developed using the Nuclear Regulatory Commission (NRC) thermal hydraulic transient code TRAC/RELAP Advanced Computational Engine (TRACE). The TRACE model includes all of the primary components: the core, downcomer, hot legs, cold legs, pumps, direct reactor auxiliary cooling system (DRACS), the primary heat exchangers (PHXs), etc. The TRACE model was used to help define and size systems such as the DRACS and the PHX. A loss of flow transient was also simulated to evaluate the performance of the reactor during an anticipated transient event. Some initial recommendations for modifying system component designs are also discussed. Finally, the TRACE model will be used as the basis for developing more detailed designs and ultimately will be used to perform transient safety analysis for the reactor.},
doi = {10.1016/j.nucengdes.2015.08.017},
journal = {Nuclear Engineering and Design},
issn = {0029-5493},
number = C,
volume = 294,
place = {United States},
year = {2015},
month = {9}
}