Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident

Safety analysis of a PWR fuelled with ATF (Accident-Tolerant Fuel) has been performed at LB-LOCA condition. The ATF being used is uranium silicide (U3Si2) and FCMF (Fully Ceramic Microencapsulated Fuel) with silicon carbide (SiC) and FeCrAl alloy as a cladding material. The objective of this researc...

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Main Author: Agung, Alexander
Format: Article
Language:English
Published: Inderscience 2018
Subjects:
Online Access:https://repository.ugm.ac.id/274995/1/IJNEST%20-%20Repository.pdf
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author Agung, Alexander
author_facet Agung, Alexander
author_sort Agung, Alexander
collection UGM
description Safety analysis of a PWR fuelled with ATF (Accident-Tolerant Fuel) has been performed at LB-LOCA condition. The ATF being used is uranium silicide (U3Si2) and FCMF (Fully Ceramic Microencapsulated Fuel) with silicon carbide (SiC) and FeCrAl alloy as a cladding material. The objective of this research is to obtain dynamic characteristics of ATF-fuelled PWR at LB-LOCA condition. RELAP5-3D system code was used to model the reactor and simulate the transient. A safe shutdown of the reactor was assumed after a depressurisation following a double-ended guillotine breach in the main pipe. The results of simulations show that during LB-LOCA with partially functioning ECCS, the transient PCTs were far below the maximum allowable limit. The use of ATF could decrease the maximum transient PCT. It is shown that U3Si2 fuel with FeCrAl cladding has the minimum PCT transient and the shortest quench time to steady state condition after transient initiation.
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spelling oai:generic.eprints.org:2749952019-01-31T01:01:44Z https://repository.ugm.ac.id/274995/ Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident Agung, Alexander Computational Heat Transfer Safety analysis of a PWR fuelled with ATF (Accident-Tolerant Fuel) has been performed at LB-LOCA condition. The ATF being used is uranium silicide (U3Si2) and FCMF (Fully Ceramic Microencapsulated Fuel) with silicon carbide (SiC) and FeCrAl alloy as a cladding material. The objective of this research is to obtain dynamic characteristics of ATF-fuelled PWR at LB-LOCA condition. RELAP5-3D system code was used to model the reactor and simulate the transient. A safe shutdown of the reactor was assumed after a depressurisation following a double-ended guillotine breach in the main pipe. The results of simulations show that during LB-LOCA with partially functioning ECCS, the transient PCTs were far below the maximum allowable limit. The use of ATF could decrease the maximum transient PCT. It is shown that U3Si2 fuel with FeCrAl cladding has the minimum PCT transient and the shortest quench time to steady state condition after transient initiation. Inderscience 2018-08-10 Article PeerReviewed application/pdf en https://repository.ugm.ac.id/274995/1/IJNEST%20-%20Repository.pdf Agung, Alexander (2018) Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident. International Journal of Nuclear Energy Science and Technology, 12 (2). pp. 196-212. ISSN 1741-637X https://www.inderscience.com/info/inarticle.php?artid=94287 https://doi.org/10.1504/IJNEST.2018.10015409
spellingShingle Computational Heat Transfer
Agung, Alexander
Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident
title Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident
title_full Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident
title_fullStr Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident
title_full_unstemmed Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident
title_short Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident
title_sort prediction of peak cladding temperature in a three loop pressurised water reactor with accident tolerant fuel during loss of coolant accident
topic Computational Heat Transfer
url https://repository.ugm.ac.id/274995/1/IJNEST%20-%20Repository.pdf
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