Velocity distribution in the subchannels of a pin bundle with a wrapping wire. Evaluation of the Reynolds number dependence in a three-pin bundle
- 1. Japan Atomic Energy Agency, Sector of Fast Reactor and Advanced Reactor Research and Development, Oarai, Ibaraki (Japan)
- 2. Ascend Co., Ltd., Tokai, Ibaraki (Japan)
Description
A sodium-cooled fast reactor has been designed to attain a high burn-up core in commercialized fast reactor cycle systems. The sodium-cooled fast reactor adopts a wire spacer between fuel pins. The wire spacer performs functions of securing the coolant channel and mixing between subchannels. In high burn-up fuel subassemblies, the fuel pin deformation due to swelling and thermal bowing may decrease the local flow velocity in the subassembly and influence the heat removal capability. Therefore, understanding the flow field in a wire-wrapped pin bundle is important. This study performed particle image velocimetry (PIV) measurements using a wire-wrapped three-pin bundle water model to grasp the flow field in the subchannel under conditions, including the laminar to turbulent regions. The PIV results confirmed that the normalized flow velocity near the wrapping wire in the low Re number condition was relatively decreased compared to that in the high Re number condition. Meanwhile, in the region away from the wrapping wire, the maximum flow velocity was increased by decreasing the Re number. Accordingly, the PIV measurements using the three-pin bundle geometry without the wrapping wire were also conducted to understand the effect of the wrapping wires on the flow field in the subchannel. The results confirmed that the mixing due to the wrapping wire occurred, even in the laminar condition. These experimental results are useful not only for understanding the pin bundle thermal hydraulics, but also for the code validation. (author)
Availability note (English)
Available from DOI: https://doi.org/10.1299/mej.20-00547Additional details
Identifiers
- DOI
- 10.1299/mej.20-00547;
Publishing Information
- Journal Title
- Mechanical Engineering Journal (Online)
- Journal Volume
- 8
- Journal Issue
- 4
- Journal Page Range
- p. 20.00547.1-20.00547.11
- ISSN
- 2187-9745
Conference
- Title
- ASME's nuclear engineering conference powered by ICONE (Online)
- Acronym
- ICONE 2020
- Dates
- 4-5 Aug 2020
- Place
- United States (United States)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53110336
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CORRELATIONS; FLOW VISUALIZATION; FUEL ELEMENT CLUSTERS; FUEL PINS; LASER RADIATION; LIGHT TRANSMISSION; MONJU REACTOR; REYNOLDS NUMBER; SPACERS; TURBULENT FLOW; VELOCIMETERS
- Descriptors DEC
- BREEDER REACTORS; DIMENSIONLESS NUMBERS; ELECTROMAGNETIC RADIATION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; FUEL ASSEMBLIES; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MEASURING INSTRUMENTS; POWER REACTORS; RADIATIONS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS; TRANSMISSION
Optional Information
- Notes
- 13 refs., 9 figs., 4 tabs.; This symposium was held online