Probabilistic risk assessment (PRA) on supercritical water cooled reactors (SCWRs)

Nuclear energy is attracting more and more attention in recent decades because of its high efficiency. The supercritical water reactor (SCWR) is a theoretical concept of future nuclear reactors. It is designed based on the existing CANada Deuterium Uranium (CANDU). For nuclear power plants, safety c...

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Bibliographic Details
Main Author: Lin, Yan Jing
Other Authors: Zhang Yue Ping
Format: Final Year Project (FYP)
Language:English
Published: 2015
Subjects:
Online Access:http://hdl.handle.net/10356/63582
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author Lin, Yan Jing
author2 Zhang Yue Ping
author_facet Zhang Yue Ping
Lin, Yan Jing
author_sort Lin, Yan Jing
collection NTU
description Nuclear energy is attracting more and more attention in recent decades because of its high efficiency. The supercritical water reactor (SCWR) is a theoretical concept of future nuclear reactors. It is designed based on the existing CANada Deuterium Uranium (CANDU). For nuclear power plants, safety concern is very important. In this project, the comparison between CANDU and SCWR design are made to highlight the advanced characteristics and safety guarantees of SCWR. Probabilistic risk assessment (PRA) is the main method involved to provide logical and numerical support of assessment result. Even though SCWR is currently in pre-conceptual phase, PRA can provide safety reference and suggest design improvement. Future study can also be conducted based on this safety analysis.
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spelling ntu-10356/635822023-07-07T17:41:51Z Probabilistic risk assessment (PRA) on supercritical water cooled reactors (SCWRs) Lin, Yan Jing Zhang Yue Ping School of Electrical and Electronic Engineering DRNTU::Engineering::Electrical and electronic engineering Nuclear energy is attracting more and more attention in recent decades because of its high efficiency. The supercritical water reactor (SCWR) is a theoretical concept of future nuclear reactors. It is designed based on the existing CANada Deuterium Uranium (CANDU). For nuclear power plants, safety concern is very important. In this project, the comparison between CANDU and SCWR design are made to highlight the advanced characteristics and safety guarantees of SCWR. Probabilistic risk assessment (PRA) is the main method involved to provide logical and numerical support of assessment result. Even though SCWR is currently in pre-conceptual phase, PRA can provide safety reference and suggest design improvement. Future study can also be conducted based on this safety analysis. Bachelor of Engineering 2015-05-15T04:28:13Z 2015-05-15T04:28:13Z 2015 2015 Final Year Project (FYP) http://hdl.handle.net/10356/63582 en Nanyang Technological University 43 p. application/pdf
spellingShingle DRNTU::Engineering::Electrical and electronic engineering
Lin, Yan Jing
Probabilistic risk assessment (PRA) on supercritical water cooled reactors (SCWRs)
title Probabilistic risk assessment (PRA) on supercritical water cooled reactors (SCWRs)
title_full Probabilistic risk assessment (PRA) on supercritical water cooled reactors (SCWRs)
title_fullStr Probabilistic risk assessment (PRA) on supercritical water cooled reactors (SCWRs)
title_full_unstemmed Probabilistic risk assessment (PRA) on supercritical water cooled reactors (SCWRs)
title_short Probabilistic risk assessment (PRA) on supercritical water cooled reactors (SCWRs)
title_sort probabilistic risk assessment pra on supercritical water cooled reactors scwrs
topic DRNTU::Engineering::Electrical and electronic engineering
url http://hdl.handle.net/10356/63582
work_keys_str_mv AT linyanjing probabilisticriskassessmentpraonsupercriticalwatercooledreactorsscwrs