Desain Reaktor Nuklir Bermoderator Air Berat Berpendingin Uap Panas Lanjut yang Memiliki Sifat Keselamatan Melekat
Abstract The problem of positive power feedback in the recent PHWR-CANDU design will be overcome by the use of "dual moderator concept ", in which two moderator systems are used, i.e. a main moderator outside the calandria tube and an annular moderator inside the annular space. The numeric...
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| Format: | Article |
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[Yogyakarta] : Universitas Gadjah Mada
2007
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| _version_ | 1797019327861358592 |
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| author | Perpustakaan UGM, i-lib |
| author_facet | Perpustakaan UGM, i-lib |
| author_sort | Perpustakaan UGM, i-lib |
| collection | UGM |
| description | Abstract
The problem of positive power feedback in the recent PHWR-CANDU design will be
overcome by the use of "dual moderator concept ", in which two moderator systems are used,
i.e. a main moderator outside the calandria tube and an annular moderator inside the annular
space. The numerical calculations have been performed for two core design namely HWR-DMST
and HWR-DM-X1 which can reach burn up of 16000 and 17500 MWd / ton U respectively.
The results for the two designs is that the values of k at fully anular moderator filling condition
are 1.0054 (HWR-DM-ST) and 1.0019 (HWR-DM-X1), while at completelly empty annular
moderator condition are 0.9634 (HWR-DM-ST) and 0.9143 (HWR-DM-X1). The decreasing of
coolant flow rate from 3043 kg/s to 853 kg/s gives a decreasing of k values of O.0109 (HWRDM-
ST) and 0.0232 (HWR-DM-X1). The increasing of inlet coolant enthalpifrom 2950 kJ/kg to
3175 kJ/kg gives a decreasing ofk values of 0.0074 (HWR-DM-ST) and 0.0239 (HWR-DM-X1).
Thus it can be summarized that these HWR-DM designs have negative power reactivity
feedback. These designs can achieve a thermal efficiencies of 38,5 % with the fuel utilizations of
120,75 and 110,52 kg of natural uranium / kWe-year for HWR-DM-ST and HWR-DM-X1
respectively.
Keywords: PHWR-CANDU, dual moderator concept |
| first_indexed | 2024-03-05T23:07:43Z |
| format | Article |
| id | oai:generic.eprints.org:25722 |
| institution | Universiti Gadjah Mada |
| last_indexed | 2024-03-13T18:57:53Z |
| publishDate | 2007 |
| publisher | [Yogyakarta] : Universitas Gadjah Mada |
| record_format | dspace |
| spelling | oai:generic.eprints.org:257222014-06-18T00:25:13Z https://repository.ugm.ac.id/25722/ Desain Reaktor Nuklir Bermoderator Air Berat Berpendingin Uap Panas Lanjut yang Memiliki Sifat Keselamatan Melekat Perpustakaan UGM, i-lib Jurnal i-lib UGM Abstract The problem of positive power feedback in the recent PHWR-CANDU design will be overcome by the use of "dual moderator concept ", in which two moderator systems are used, i.e. a main moderator outside the calandria tube and an annular moderator inside the annular space. The numerical calculations have been performed for two core design namely HWR-DMST and HWR-DM-X1 which can reach burn up of 16000 and 17500 MWd / ton U respectively. The results for the two designs is that the values of k at fully anular moderator filling condition are 1.0054 (HWR-DM-ST) and 1.0019 (HWR-DM-X1), while at completelly empty annular moderator condition are 0.9634 (HWR-DM-ST) and 0.9143 (HWR-DM-X1). The decreasing of coolant flow rate from 3043 kg/s to 853 kg/s gives a decreasing of k values of O.0109 (HWRDM- ST) and 0.0232 (HWR-DM-X1). The increasing of inlet coolant enthalpifrom 2950 kJ/kg to 3175 kJ/kg gives a decreasing ofk values of 0.0074 (HWR-DM-ST) and 0.0239 (HWR-DM-X1). Thus it can be summarized that these HWR-DM designs have negative power reactivity feedback. These designs can achieve a thermal efficiencies of 38,5 % with the fuel utilizations of 120,75 and 110,52 kg of natural uranium / kWe-year for HWR-DM-ST and HWR-DM-X1 respectively. Keywords: PHWR-CANDU, dual moderator concept [Yogyakarta] : Universitas Gadjah Mada 2007 Article NonPeerReviewed Perpustakaan UGM, i-lib (2007) Desain Reaktor Nuklir Bermoderator Air Berat Berpendingin Uap Panas Lanjut yang Memiliki Sifat Keselamatan Melekat. Jurnal i-lib UGM. http://i-lib.ugm.ac.id/jurnal/download.php?dataId=8722 |
| spellingShingle | Jurnal i-lib UGM Perpustakaan UGM, i-lib Desain Reaktor Nuklir Bermoderator Air Berat Berpendingin Uap Panas Lanjut yang Memiliki Sifat Keselamatan Melekat |
| title | Desain Reaktor Nuklir Bermoderator Air Berat Berpendingin Uap Panas Lanjut yang Memiliki Sifat Keselamatan Melekat |
| title_full | Desain Reaktor Nuklir Bermoderator Air Berat Berpendingin Uap Panas Lanjut yang Memiliki Sifat Keselamatan Melekat |
| title_fullStr | Desain Reaktor Nuklir Bermoderator Air Berat Berpendingin Uap Panas Lanjut yang Memiliki Sifat Keselamatan Melekat |
| title_full_unstemmed | Desain Reaktor Nuklir Bermoderator Air Berat Berpendingin Uap Panas Lanjut yang Memiliki Sifat Keselamatan Melekat |
| title_short | Desain Reaktor Nuklir Bermoderator Air Berat Berpendingin Uap Panas Lanjut yang Memiliki Sifat Keselamatan Melekat |
| title_sort | desain reaktor nuklir bermoderator air berat berpendingin uap panas lanjut yang memiliki sifat keselamatan melekat |
| topic | Jurnal i-lib UGM |
| work_keys_str_mv | AT perpustakaanugmilib desainreaktornuklirbermoderatorairberatberpendinginuappanaslanjutyangmemilikisifatkeselamatanmelekat |