Coupled analysis and improvements for Canadian-SCWR core design
- 1. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049 (China)
- 2. Key Laboratory of Thermo-Fluid Science and Engineering of MOE, School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an, Shaanxi 710049 (China)
Description
Highlights: • Coupled neutronics/thermal hydraulics analysis for recent Canadian-SCWR. • Coolant density variation inside central flow tube of assembly was considered. • An improved core design for Canadian-SCWR. • Lower MCST and more flat radial power distribution. - Abstract: A coupled neutronics and thermal hydraulics analysis have been done for the recent Canadian SCWR, high efficiency re-entrant channel (HERC) design. The neutronics analysis was carried out by using a 3D fine mesh diffusion theory code and thermal hydraulics calculations were done by using single channel model. These two codes were coupled with each other by a link code. The axial variation of water density in the central flow tube has also been considered in the analysis. The maximum clad surface temperature for the original design was calculated to be very high, so some improvements in the channel design have also been proposed in this study. Moreover, a new core-loading scheme has been searched in order to get more flat radial power distribution and lower cladding surface temperature
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2013.12.045Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2013.12.045;
- PII
- S0029-5493(14)00002-8;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 268
- Journal Page Range
- p. 104-112
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46019478
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- CANADA; CLADDING; COOLANTS; DENSITY; NEUTRON DIFFUSION EQUATION; POWER DISTRIBUTION; REACTOR CORES; REACTOR FUELING; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TUBES; WATER; WATER COOLED REACTORS
- Descriptors DEC
- DEPOSITION; DEVELOPED COUNTRIES; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; NORTH AMERICA; OXYGEN COMPOUNDS; PARTIAL DIFFERENTIAL EQUATIONS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; SURFACE COATING
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.