Effect of Flow Blockage on the Coolability during Reflood in a 2 × 2 Rod Bundle
During the reflood phase of a large-break loss-of-coolant accident (LBLOCA) in a pressurized-water reactor (PWR), the fuel rods can be ballooned or rearranged owing to an increase in the temperature and internal pressure of the fuel rods. In this study, an experimental study was performed to underst...
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| Format: | Article |
| Language: | English |
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Wiley
2014-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2014/247862 |
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| author | Kihwan Kim Byung-Jae Kim Young-Jung Youn Hae-Seob Choi Sang-Ki Moon Chul-Hwa Song |
| author_facet | Kihwan Kim Byung-Jae Kim Young-Jung Youn Hae-Seob Choi Sang-Ki Moon Chul-Hwa Song |
| author_sort | Kihwan Kim |
| collection | DOAJ |
| description | During the reflood phase of a large-break loss-of-coolant accident (LBLOCA) in a pressurized-water reactor (PWR), the fuel rods can be ballooned or rearranged owing to an increase in the temperature and internal pressure of the fuel rods. In this study, an experimental study was performed to understand the thermal behavior and effect of the ballooned region on the coolability using a 2 × 2 rod bundle test facility. The electrically heated rod bundle was used and the ballooning shape of the rods was simulated by superimposing hollow sleeves, which have a 90% blockage ratio. Forced reflood tests were performed to examine the transient two-phase heat transfer behavior for different reflood rates and rod powers. The droplet behaviors were also investigated by measuring the velocity and size of droplets near the blockage region. The results showed that the heat transfer was enhanced in the downstream of the blockage region, owing to the reduced flow area of the subchannel, intensification of turbulence, and deposition of the droplet. |
| format | Article |
| id | doaj-art-5bd0d68b060841a6908ce942e10b7c76 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2014-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-5bd0d68b060841a6908ce942e10b7c762025-08-20T03:34:48ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832014-01-01201410.1155/2014/247862247862Effect of Flow Blockage on the Coolability during Reflood in a 2 × 2 Rod BundleKihwan Kim0Byung-Jae Kim1Young-Jung Youn2Hae-Seob Choi3Sang-Ki Moon4Chul-Hwa Song5Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-Gu, Daejeon 305-353, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-Gu, Daejeon 305-353, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-Gu, Daejeon 305-353, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-Gu, Daejeon 305-353, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-Gu, Daejeon 305-353, Republic of KoreaKorea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-Gu, Daejeon 305-353, Republic of KoreaDuring the reflood phase of a large-break loss-of-coolant accident (LBLOCA) in a pressurized-water reactor (PWR), the fuel rods can be ballooned or rearranged owing to an increase in the temperature and internal pressure of the fuel rods. In this study, an experimental study was performed to understand the thermal behavior and effect of the ballooned region on the coolability using a 2 × 2 rod bundle test facility. The electrically heated rod bundle was used and the ballooning shape of the rods was simulated by superimposing hollow sleeves, which have a 90% blockage ratio. Forced reflood tests were performed to examine the transient two-phase heat transfer behavior for different reflood rates and rod powers. The droplet behaviors were also investigated by measuring the velocity and size of droplets near the blockage region. The results showed that the heat transfer was enhanced in the downstream of the blockage region, owing to the reduced flow area of the subchannel, intensification of turbulence, and deposition of the droplet.http://dx.doi.org/10.1155/2014/247862 |
| spellingShingle | Kihwan Kim Byung-Jae Kim Young-Jung Youn Hae-Seob Choi Sang-Ki Moon Chul-Hwa Song Effect of Flow Blockage on the Coolability during Reflood in a 2 × 2 Rod Bundle Science and Technology of Nuclear Installations |
| title | Effect of Flow Blockage on the Coolability during Reflood in a 2 × 2 Rod Bundle |
| title_full | Effect of Flow Blockage on the Coolability during Reflood in a 2 × 2 Rod Bundle |
| title_fullStr | Effect of Flow Blockage on the Coolability during Reflood in a 2 × 2 Rod Bundle |
| title_full_unstemmed | Effect of Flow Blockage on the Coolability during Reflood in a 2 × 2 Rod Bundle |
| title_short | Effect of Flow Blockage on the Coolability during Reflood in a 2 × 2 Rod Bundle |
| title_sort | effect of flow blockage on the coolability during reflood in a 2 2 rod bundle |
| url | http://dx.doi.org/10.1155/2014/247862 |
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