Heat removal and hybrid ventilation characteristics of a vertical dry storage cask for spent nuclear fuel
- 1. Department of Civil Engineering, National Cheng-Kung University, Taiwan, 1, University Road, Tainan City 701, Taiwan, ROC (China)
- 2. Fuel Cycle and Materials Administration, Atomic Energy Council, Taiwan, 80, Sec 1, Chenggong Rd., New Taipei City 234, Taiwan, ROC (China)
- 3. Department of Civil Engineering, National Chung Hsing University, Taiwan, 145, Xingda Rd., Taichung City 402, Taiwan, ROC (China)
Description
Highlights: • Avertical dry storage cask for spent nuclear fuelis our target. • Heat removal and hybrid ventilation characteristicswerenumericallyinvestigated. • Buoyant airflow dominated heat removal at low Re (2.7 × 104). • When Re = 5.3 × 104–1.3 × 105, wind-induced airflow compromised the buoyant one. • When Re ≥2.7 × 105, wind-induced airflow dominated and heat removal increased. Computational fluid dynamics (CFD) was used in this study to numerically simulate the heat removal and hybrid ventilation characteristics of a vertical dry storage cask for spent nuclear fuel. The parameters included a Grashof number of 1.0x1011, an approaching wind incidence angle of 0° or 45°, and a Reynolds number (Re) of (). As shown by the results, the buoyant airflow dominated the heat removal capability of the cask at low Re (). When the Re was increased to , the wind-induced channel airflow compromised the buoyant airflow, thus reducing the heat removal capacity of the cask. When the Re was, the wind-induced airflow dominated.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2021.111183Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2021.111183;
- PII
- S0029549321001357;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 378
- Journal Page Range
- vp.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54083768
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- AIR FLOW; COMPUTERIZED SIMULATION; DRY STORAGE; FLUID MECHANICS; GRASHOF NUMBER; HEAT; HEAT TRANSFER; INCIDENCE ANGLE; REYNOLDS NUMBER; SPENT FUELS
- Descriptors DEC
- DIMENSIONLESS NUMBERS; ENERGY; ENERGY SOURCES; ENERGY TRANSFER; FLUID FLOW; FUELS; GAS FLOW; MATERIALS; MECHANICS; NUCLEAR FUELS; REACTOR MATERIALS; SIMULATION; STORAGE
Optional Information
- Copyright
- Copyright (c) 2021 Elsevier B.V. All rights reserved.