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Title: CFD Analysis of Upper Plenum Flow for a Sodium-Cooled Small Modular Reactor

Abstract

Upper plenum flow behavior is important for many operational and safety issues in sodium fast reactors. The Prototype Gen-IV Sodium Fast Reactor (PGSFR), a pool-type, 150 MWe output power design, was used as a reference case for a detailed characterization of upper plenum flow for normal operating conditions. Computational Fluid Dynamics (CFD) simulation was utilized with detailed geometric modeling of major structures. Core outlet conditions based on prior system-level calculations were mapped to approximate the outlet temperatures and flow rates for each core assembly. Core outlet flow was found to largely bypass the Upper Internal Structures (UIS). Flow curves over the shield and circulates within the pool before exiting the plenum. Cross-flows and temperatures were evaluated near the core outlet, leading to a proposed height for the core outlet thermocouples to ensure accurate assembly-specific temperature readings. A passive scalar was used to evaluate fluid residence time from core outlet to IHX inlet, which can be used to assess the applicability of various methods for monitoring fuel failure. Additionally, the gas entrainment likelihood was assessed based on the CFD simulation results. Based on the evaluation of velocity gradients and turbulent kinetic energies and the available gas entrainment criteria in the literature,more » it was concluded that significant gas entrainment is unlikely for the current PGSFR design.« less

Authors:
;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
KAERI (Korea Atomic Energy Research Institute)
OSTI Identifier:
1336451
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Conference
Resource Relation:
Conference: 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), 08/30/15 - 09/04/15, Chicago, IL, US
Country of Publication:
United States
Language:
English
Subject:
UIS; computational fluid dynamics; gas entrainment; sodium fast reactor; upper plenum

Citation Formats

Kraus, A., and Hu, R. CFD Analysis of Upper Plenum Flow for a Sodium-Cooled Small Modular Reactor. United States: N. p., 2015. Web.
Kraus, A., & Hu, R. CFD Analysis of Upper Plenum Flow for a Sodium-Cooled Small Modular Reactor. United States.
Kraus, A., and Hu, R. Thu . "CFD Analysis of Upper Plenum Flow for a Sodium-Cooled Small Modular Reactor". United States. doi:.
@article{osti_1336451,
title = {CFD Analysis of Upper Plenum Flow for a Sodium-Cooled Small Modular Reactor},
author = {Kraus, A. and Hu, R.},
abstractNote = {Upper plenum flow behavior is important for many operational and safety issues in sodium fast reactors. The Prototype Gen-IV Sodium Fast Reactor (PGSFR), a pool-type, 150 MWe output power design, was used as a reference case for a detailed characterization of upper plenum flow for normal operating conditions. Computational Fluid Dynamics (CFD) simulation was utilized with detailed geometric modeling of major structures. Core outlet conditions based on prior system-level calculations were mapped to approximate the outlet temperatures and flow rates for each core assembly. Core outlet flow was found to largely bypass the Upper Internal Structures (UIS). Flow curves over the shield and circulates within the pool before exiting the plenum. Cross-flows and temperatures were evaluated near the core outlet, leading to a proposed height for the core outlet thermocouples to ensure accurate assembly-specific temperature readings. A passive scalar was used to evaluate fluid residence time from core outlet to IHX inlet, which can be used to assess the applicability of various methods for monitoring fuel failure. Additionally, the gas entrainment likelihood was assessed based on the CFD simulation results. Based on the evaluation of velocity gradients and turbulent kinetic energies and the available gas entrainment criteria in the literature, it was concluded that significant gas entrainment is unlikely for the current PGSFR design.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 2015},
month = {Thu Jan 01 00:00:00 EST 2015}
}

Conference:
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