Study on the lead cooled fast reactor (LFR) design

The demand for new and advance nuclear systems are widely studied all over the world. By the late 2002, under the Generation IV International Forum (GIF) which is an international collective represented by thirteen countries, an international task force was tasked with the research and development o...

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Main Author: Quek, Ernest Tze Yeor
Other Authors: Fan Weijun
Format: Final Year Project
Language:English
Published: 2015
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Online Access:http://hdl.handle.net/10356/63408
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Institution: Nanyang Technological University
Language: English
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spelling sg-ntu-dr.10356-634082023-07-07T16:22:47Z Study on the lead cooled fast reactor (LFR) design Quek, Ernest Tze Yeor Fan Weijun School of Electrical and Electronic Engineering DRNTU::Engineering::Electrical and electronic engineering The demand for new and advance nuclear systems are widely studied all over the world. By the late 2002, under the Generation IV International Forum (GIF) which is an international collective represented by thirteen countries, an international task force was tasked with the research and development of the six nuclear reactor technologies for the future. One of the six Generation IV nuclear reactor is the Lead cooled Fast Reactor. This paper provide an overview of the design features for Lead Fast Reactor (LFR) which will cover two pool-type reactor concepts. One of them is the Small Secure Transportable Autonomous Reactor (SSTAR) while the other is the European Lead-cooled System (ELSY). One of the utmost essential features of LFR is the liquid lead which acts as a coolant for the reactor. With this unique element being used in the system, it allows a greater advantage which coincides to the GIF main focus which is in economics, sustainability, safety, reliability and proliferation-resistance. Pure lead has a high boiling point of 1745 which give a favorable advantage to the security of the system. On the contrary, its melting point of 327.4 is considered to be too high which requires new innovative methods to counter the coolant from freezing and blockage of the circulation throughout the core. At high temperatures, it is necessary to control its purity carefully as it is relatively corrosive towards structural materials. Being used in harsh environment coupled with high energy neutrons effects, it is advisable to make a right choice of material. The main designed features of the ELSY and SSTAR system will be investigated and summarized. Also the key design challenge issues of each system will be presented. Bachelor of Engineering 2015-05-13T06:38:21Z 2015-05-13T06:38:21Z 2015 2015 Final Year Project (FYP) http://hdl.handle.net/10356/63408 en Nanyang Technological University 58 p. application/pdf
institution Nanyang Technological University
building NTU Library
continent Asia
country Singapore
Singapore
content_provider NTU Library
collection DR-NTU
language English
topic DRNTU::Engineering::Electrical and electronic engineering
spellingShingle DRNTU::Engineering::Electrical and electronic engineering
Quek, Ernest Tze Yeor
Study on the lead cooled fast reactor (LFR) design
description The demand for new and advance nuclear systems are widely studied all over the world. By the late 2002, under the Generation IV International Forum (GIF) which is an international collective represented by thirteen countries, an international task force was tasked with the research and development of the six nuclear reactor technologies for the future. One of the six Generation IV nuclear reactor is the Lead cooled Fast Reactor. This paper provide an overview of the design features for Lead Fast Reactor (LFR) which will cover two pool-type reactor concepts. One of them is the Small Secure Transportable Autonomous Reactor (SSTAR) while the other is the European Lead-cooled System (ELSY). One of the utmost essential features of LFR is the liquid lead which acts as a coolant for the reactor. With this unique element being used in the system, it allows a greater advantage which coincides to the GIF main focus which is in economics, sustainability, safety, reliability and proliferation-resistance. Pure lead has a high boiling point of 1745 which give a favorable advantage to the security of the system. On the contrary, its melting point of 327.4 is considered to be too high which requires new innovative methods to counter the coolant from freezing and blockage of the circulation throughout the core. At high temperatures, it is necessary to control its purity carefully as it is relatively corrosive towards structural materials. Being used in harsh environment coupled with high energy neutrons effects, it is advisable to make a right choice of material. The main designed features of the ELSY and SSTAR system will be investigated and summarized. Also the key design challenge issues of each system will be presented.
author2 Fan Weijun
author_facet Fan Weijun
Quek, Ernest Tze Yeor
format Final Year Project
author Quek, Ernest Tze Yeor
author_sort Quek, Ernest Tze Yeor
title Study on the lead cooled fast reactor (LFR) design
title_short Study on the lead cooled fast reactor (LFR) design
title_full Study on the lead cooled fast reactor (LFR) design
title_fullStr Study on the lead cooled fast reactor (LFR) design
title_full_unstemmed Study on the lead cooled fast reactor (LFR) design
title_sort study on the lead cooled fast reactor (lfr) design
publishDate 2015
url http://hdl.handle.net/10356/63408
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