High fidelity core flow measurement experiment for an advanced research reactor using a real scale mockup
Owing to spatial effects and vortex flow, flow in research reactors that use plate-type fuels can be maldistributed to the parallel channels of the core, which significantly impacts the reactor safety. In this study, the core flow of an advanced research reactor was measured in a real-scale facility...
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| Published in | Nuclear engineering and technology Vol. 56; no. 9; pp. 3700 - 3716 |
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| Main Authors | , , , , , , , , , , , |
| Format | Journal Article |
| Language | English |
| Published |
Elsevier B.V
01.09.2024
Elsevier 한국원자력학회 |
| Subjects | |
| Online Access | Get full text |
| ISSN | 1738-5733 2234-358X |
| DOI | 10.1016/j.net.2024.04.019 |
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| Abstract | Owing to spatial effects and vortex flow, flow in research reactors that use plate-type fuels can be maldistributed to the parallel channels of the core, which significantly impacts the reactor safety. In this study, the core flow of an advanced research reactor was measured in a real-scale facility under various hydraulic conditions. For flow measurement, integrated pressure lines were embedded in the mockups of 22 fuel assemblies and six fission molybdenum assemblies. Each assembly mockup was individually calibrated to obtain the relationship between the pressure drop and flow rate. Real-scale facility, which implements the characteristics of the hydraulic conditions in research reactors, was then used to evaluate the assembly-to-assembly flow distribution under normal operating condition, a partially withdrawn condition for the follower fuel assemblies, no flow for the pool water management system, and 1:1.5 asymmetric inlet flow condition. As a parallel channel system, core flow distribution was analyzed with conventional header design approach. Taking into account the measuring uncertainty, the core flow was uniformly distributed within 5 % under all conditions. This was mainly because the core flow resistance was sufficiently high and the vortex flow was minimized by the perforated plate. |
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| AbstractList | Owing to spatial effects and vortex flow, flow in research reactors that use plate-type fuels can be maldistributed to the parallel channels of the core, which significantly impacts the reactor safety. In this study, the core flow of an advanced research reactor was measured in a real-scale facility under various hydraulic conditions. For flow measurement, integrated pressure lines were embedded in the mockups of 22 fuel assemblies and six fission molybdenum assemblies. Each assembly mockup was individually calibrated to obtain the relationship between the pressure drop and flow rate. Real-scale facility, which implements the characteristics of the hydraulic conditions in research reactors, was then used to evaluate the assembly-to-assembly flow distribution under normal operating condition, a partially withdrawn condition for the follower fuel assemblies, no flow for the pool water management system, and 1:1.5 asymmetric inlet flow condition. As a parallel channel system, core flow distribution was analyzed with conventional header design approach. Taking into account the measuring uncertainty, the core flow was uniformly distributed within 5 % under all conditions. This was mainly because the core flow resistance was sufficiently high and the vortex flow was minimized by the perforated plate. Owing to spatial effects and vortex flow, flow in research reactors that use plate-type fuels can be maldistributed to the parallel channels of the core, which significantly impacts the reactor safety. In this study, the core flow of an advanced research reactor was measured in a real-scale facility under various hydraulic conditions. For flow measurement, integrated pressure lines were embedded in the mockups of 22 fuel assemblies and six fission molybdenum assemblies. Each assembly mockup was individually calibrated to obtain the relationship between the pressure drop and flow rate. Real-scale facility, which implements the characteristics of the hydraulic conditions in research reactors, was then used to evaluate the assembly-to-assembly flow distribution under normal operating condition, a partially withdrawn condition for the follower fuel assemblies, no flow for the pool water management system, and 1:1.5 asymmetric inlet flow condition. As a parallel channel system, core flow distribution was analyzed with conventional header design approach. Taking into account the measuring uncertainty, the core flow was uniformly distributed within 5 % under all conditions. This was mainly because the core flow resistance was sufficiently high and the vortex flow was minimized by the perforated plate. KCI Citation Count: 0 |
| Author | Choi, Nakjun Kim, Huiyung Hwang, Donkoan Song, Kiwon Lee, Yohan Jo, HangJin Kim, Taeil Jung, WooHyun Kim, Jihun Son, Hyung Min Chung, Seong Seok Park, Jonghark |
| Author_xml | – sequence: 1 givenname: Taeil surname: Kim fullname: Kim, Taeil organization: Department of Mechanical Engineering, POSTECH, Pohang, 790-784, Republic of Korea – sequence: 2 givenname: Yohan surname: Lee fullname: Lee, Yohan organization: Division of Advanced Nuclear Engineering, POSTECH, Pohang, 790-784, Republic of Korea – sequence: 3 givenname: Donkoan surname: Hwang fullname: Hwang, Donkoan organization: Division of Advanced Nuclear Engineering, POSTECH, Pohang, 790-784, Republic of Korea – sequence: 4 givenname: WooHyun surname: Jung fullname: Jung, WooHyun organization: Department of Mechanical Engineering, POSTECH, Pohang, 790-784, Republic of Korea – sequence: 5 givenname: Nakjun surname: Choi fullname: Choi, Nakjun organization: Division of Advanced Nuclear Engineering, POSTECH, Pohang, 790-784, Republic of Korea – sequence: 6 givenname: Seong Seok surname: Chung fullname: Chung, Seong Seok organization: Division of Advanced Nuclear Engineering, POSTECH, Pohang, 790-784, Republic of Korea – sequence: 7 givenname: Jihun surname: Kim fullname: Kim, Jihun organization: Department of Mechanical Engineering, POSTECH, Pohang, 790-784, Republic of Korea – sequence: 8 givenname: Jonghark surname: Park fullname: Park, Jonghark organization: Korea Atomic Energy Research Institute, Daejeon, 989-111, Republic of Korea – sequence: 9 givenname: Hyung Min orcidid: 0000-0003-4360-5045 surname: Son fullname: Son, Hyung Min organization: Korea Atomic Energy Research Institute, Daejeon, 989-111, Republic of Korea – sequence: 10 givenname: Kiwon surname: Song fullname: Song, Kiwon organization: Korea Atomic Energy Research Institute, Daejeon, 989-111, Republic of Korea – sequence: 11 givenname: Huiyung surname: Kim fullname: Kim, Huiyung organization: Korea Atomic Energy Research Institute, Daejeon, 989-111, Republic of Korea – sequence: 12 givenname: HangJin orcidid: 0000-0002-8154-4418 surname: Jo fullname: Jo, HangJin email: jhj04@postech.ac.kr organization: Department of Mechanical Engineering, POSTECH, Pohang, 790-784, Republic of Korea |
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| Keywords | research reactor Pressure drop Flow distribution plate-type fuel Single-phase flow friction factor Real-scale |
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| Title | High fidelity core flow measurement experiment for an advanced research reactor using a real scale mockup |
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