INVESTIGATION OF A SELF-ACTUATED, GRAVITY-DRIVEN SHUTDOWN SYSTEM IN A SMALL LEAD-COOLED REACTOR

Passive safety systems in a nuclear reactor allow to simplify the overall plant design, beside improving economics and reliability, which are considered to be among the salient goals of advanced Generation IV reactors. This work focuses on investigating the application of a self-actuated, gravity-dr...

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Main Authors: Acharya Govatsa, Dehlin Fredrik, Bortot Sara, Mickus Ignas
Format: Article
Language:English
Published: EDP Sciences 2021-01-01
Series:EPJ Web of Conferences
Subjects:
Online Access:https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_07007.pdf
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spelling doaj-bb9ea5b58f69447dae6a7616859747522021-08-03T00:15:56ZengEDP SciencesEPJ Web of Conferences2100-014X2021-01-012470700710.1051/epjconf/202124707007epjconf_physor2020_07007INVESTIGATION OF A SELF-ACTUATED, GRAVITY-DRIVEN SHUTDOWN SYSTEM IN A SMALL LEAD-COOLED REACTORAcharya GovatsaDehlin FredrikBortot SaraMickus IgnasPassive safety systems in a nuclear reactor allow to simplify the overall plant design, beside improving economics and reliability, which are considered to be among the salient goals of advanced Generation IV reactors. This work focuses on investigating the application of a self-actuated, gravity-driven shutdown system in a small lead-cooled fast reactor and its dynamic response to an initiating event. The reactor thermal-hydraulics and neutronics assessment were performed in advance. According to a first-order approximation approach, the passive insertion of shutdown assembly was assumed to be influenced primarily by three forces: gravitational, buoyancy and fluid drag. A system of kinematic equations were formulated a priori and a MATLAB program was developed to determine the dynamics of the assembly. Identifying the delicate nature of the balance of forces, sensitivity analysis for coolant channel velocities and assembly foot densities yielded an optimal system model that resulted in successful passive shutdown. Transient safety studies, using the multi-point dynamics code BELLA, showed that the gravity-driven system acts remarkably well, even when accounting for a brief delay in self-actuation. Ultimately the reactor is brought to a sub-critical state while respecting technological constraints.https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_07007.pdfself-actuated passive systemgravity-driven shutdown systemsmall modular reactorlead-cooled fast reactor
collection DOAJ
language English
format Article
sources DOAJ
author Acharya Govatsa
Dehlin Fredrik
Bortot Sara
Mickus Ignas
spellingShingle Acharya Govatsa
Dehlin Fredrik
Bortot Sara
Mickus Ignas
INVESTIGATION OF A SELF-ACTUATED, GRAVITY-DRIVEN SHUTDOWN SYSTEM IN A SMALL LEAD-COOLED REACTOR
EPJ Web of Conferences
self-actuated passive system
gravity-driven shutdown system
small modular reactor
lead-cooled fast reactor
author_facet Acharya Govatsa
Dehlin Fredrik
Bortot Sara
Mickus Ignas
author_sort Acharya Govatsa
title INVESTIGATION OF A SELF-ACTUATED, GRAVITY-DRIVEN SHUTDOWN SYSTEM IN A SMALL LEAD-COOLED REACTOR
title_short INVESTIGATION OF A SELF-ACTUATED, GRAVITY-DRIVEN SHUTDOWN SYSTEM IN A SMALL LEAD-COOLED REACTOR
title_full INVESTIGATION OF A SELF-ACTUATED, GRAVITY-DRIVEN SHUTDOWN SYSTEM IN A SMALL LEAD-COOLED REACTOR
title_fullStr INVESTIGATION OF A SELF-ACTUATED, GRAVITY-DRIVEN SHUTDOWN SYSTEM IN A SMALL LEAD-COOLED REACTOR
title_full_unstemmed INVESTIGATION OF A SELF-ACTUATED, GRAVITY-DRIVEN SHUTDOWN SYSTEM IN A SMALL LEAD-COOLED REACTOR
title_sort investigation of a self-actuated, gravity-driven shutdown system in a small lead-cooled reactor
publisher EDP Sciences
series EPJ Web of Conferences
issn 2100-014X
publishDate 2021-01-01
description Passive safety systems in a nuclear reactor allow to simplify the overall plant design, beside improving economics and reliability, which are considered to be among the salient goals of advanced Generation IV reactors. This work focuses on investigating the application of a self-actuated, gravity-driven shutdown system in a small lead-cooled fast reactor and its dynamic response to an initiating event. The reactor thermal-hydraulics and neutronics assessment were performed in advance. According to a first-order approximation approach, the passive insertion of shutdown assembly was assumed to be influenced primarily by three forces: gravitational, buoyancy and fluid drag. A system of kinematic equations were formulated a priori and a MATLAB program was developed to determine the dynamics of the assembly. Identifying the delicate nature of the balance of forces, sensitivity analysis for coolant channel velocities and assembly foot densities yielded an optimal system model that resulted in successful passive shutdown. Transient safety studies, using the multi-point dynamics code BELLA, showed that the gravity-driven system acts remarkably well, even when accounting for a brief delay in self-actuation. Ultimately the reactor is brought to a sub-critical state while respecting technological constraints.
topic self-actuated passive system
gravity-driven shutdown system
small modular reactor
lead-cooled fast reactor
url https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_07007.pdf
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AT mickusignas investigationofaselfactuatedgravitydrivenshutdownsysteminasmallleadcooledreactor
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