Investigation on the supercritical water cooled nuclear reactor
In this report, Supercritical Water Cooled Nuclear Reactor (SCWR) is mainly discussed and compared it with the other nuclear reactors for its advantages and disadvantages. It is one of six types Gen-IV nuclear reactor designs selected by the international forum for R&D. It is the only water reac...
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sg-ntu-dr.10356-657002023-07-07T17:07:07Z Investigation on the supercritical water cooled nuclear reactor Min, Aung Myat Maw Er Meng Joo School of Electrical and Electronic Engineering DRNTU::Engineering::Nuclear engineering In this report, Supercritical Water Cooled Nuclear Reactor (SCWR) is mainly discussed and compared it with the other nuclear reactors for its advantages and disadvantages. It is one of six types Gen-IV nuclear reactor designs selected by the international forum for R&D. It is the only water reactor design among Gen-IV reactors. Preliminary study shows that the thermal efficiency can be as high as 45% for SCWR comparing with traditional reactors which have the thermal efficiencies around 30%. The latest design features together with the software simulator and safety concerns for SCWR applications are described. Bachelor of Engineering 2015-12-10T02:53:52Z 2015-12-10T02:53:52Z 2015 2015 Final Year Project (FYP) http://hdl.handle.net/10356/65700 en Nanyang Technological University 68 p. application/pdf |
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DRNTU::Engineering::Nuclear engineering Min, Aung Myat Maw Investigation on the supercritical water cooled nuclear reactor |
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In this report, Supercritical Water Cooled Nuclear Reactor (SCWR) is mainly discussed and compared it with the other nuclear reactors for its advantages and disadvantages. It is one of six types Gen-IV nuclear reactor designs selected by the international forum for R&D. It is the only water reactor design among Gen-IV reactors. Preliminary study shows that the thermal efficiency can be as high as 45% for SCWR comparing with traditional reactors which have the thermal efficiencies around 30%. The latest design features together with the software simulator and safety concerns for SCWR applications are described. |
| author2 |
Er Meng Joo |
| author_facet |
Er Meng Joo Min, Aung Myat Maw |
| format |
Final Year Project |
| author |
Min, Aung Myat Maw |
| author_sort |
Min, Aung Myat Maw |
| title |
Investigation on the supercritical water cooled nuclear reactor |
| title_short |
Investigation on the supercritical water cooled nuclear reactor |
| title_full |
Investigation on the supercritical water cooled nuclear reactor |
| title_fullStr |
Investigation on the supercritical water cooled nuclear reactor |
| title_full_unstemmed |
Investigation on the supercritical water cooled nuclear reactor |
| title_sort |
investigation on the supercritical water cooled nuclear reactor |
| publishDate |
2015 |
| url |
http://hdl.handle.net/10356/65700 |
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1772826010374373376 |