Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor
Heat transfer characteristics of fuel assemblies for a high flux research reactor with a neutron trap are numerically investigated in this study. Single-phase turbulence flow is calculated by a commercial code, FLUENT, where the computational objective covers standard and control fuel assemblies. Th...
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Format: | Article |
Language: | English |
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Wiley
2015-01-01
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Series: | Science and Technology of Nuclear Installations |
Online Access: | http://dx.doi.org/10.1155/2015/198654 |
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author | Daxin Gong Shanfang Huang Guanbo Wang Kan Wang |
author_facet | Daxin Gong Shanfang Huang Guanbo Wang Kan Wang |
author_sort | Daxin Gong |
collection | DOAJ |
description | Heat transfer characteristics of fuel assemblies for a high flux research reactor with a neutron trap are numerically investigated in this study. Single-phase turbulence flow is calculated by a commercial code, FLUENT, where the computational objective covers standard and control fuel assemblies. The simulation is carried out with an inlet coolant velocity varying from 4.5 m/s to 7.5 m/s in hot assemblies. The results indicate that the cladding temperature is always lower than the saturation temperature in the calculated ranges. The temperature rise in the control fuel assembly is smaller than that of the standard fuel assembly. Additionally, the assembly with a hot spot is specially studied, and the safety of the research reactor is also approved. |
format | Article |
id | doaj-art-b33a6a1e9681478fb00b7361a8a5b34c |
institution | Kabale University |
issn | 1687-6075 1687-6083 |
language | English |
publishDate | 2015-01-01 |
publisher | Wiley |
record_format | Article |
series | Science and Technology of Nuclear Installations |
spelling | doaj-art-b33a6a1e9681478fb00b7361a8a5b34c2025-02-03T06:07:18ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832015-01-01201510.1155/2015/198654198654Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research ReactorDaxin Gong0Shanfang Huang1Guanbo Wang2Kan Wang3Department of Engineering Physics, Tsinghua University, Beijing 100086, ChinaDepartment of Engineering Physics, Tsinghua University, Beijing 100086, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaDepartment of Engineering Physics, Tsinghua University, Beijing 100086, ChinaHeat transfer characteristics of fuel assemblies for a high flux research reactor with a neutron trap are numerically investigated in this study. Single-phase turbulence flow is calculated by a commercial code, FLUENT, where the computational objective covers standard and control fuel assemblies. The simulation is carried out with an inlet coolant velocity varying from 4.5 m/s to 7.5 m/s in hot assemblies. The results indicate that the cladding temperature is always lower than the saturation temperature in the calculated ranges. The temperature rise in the control fuel assembly is smaller than that of the standard fuel assembly. Additionally, the assembly with a hot spot is specially studied, and the safety of the research reactor is also approved.http://dx.doi.org/10.1155/2015/198654 |
spellingShingle | Daxin Gong Shanfang Huang Guanbo Wang Kan Wang Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor Science and Technology of Nuclear Installations |
title | Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor |
title_full | Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor |
title_fullStr | Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor |
title_full_unstemmed | Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor |
title_short | Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor |
title_sort | heat transfer calculation on plate type fuel assembly of high flux research reactor |
url | http://dx.doi.org/10.1155/2015/198654 |
work_keys_str_mv | AT daxingong heattransfercalculationonplatetypefuelassemblyofhighfluxresearchreactor AT shanfanghuang heattransfercalculationonplatetypefuelassemblyofhighfluxresearchreactor AT guanbowang heattransfercalculationonplatetypefuelassemblyofhighfluxresearchreactor AT kanwang heattransfercalculationonplatetypefuelassemblyofhighfluxresearchreactor |