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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Main Authors: Daxin Gong, Shanfang Huang, Guanbo Wang, Kan Wang
Format: Article
Language:English
Published: Wiley 2015-01-01
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
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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