Published January 2013
| Version v1
Journal article
Thermal-hydraulic primary numerical analysis for Pb-Bi fast reactor sub-channel
- 1. School of Energy and Power Engineering, Xi'an Jiaotong University (China)
Description
To explore the thermal-hydraulics characters of Pb-Bi fast reactor sub- channel, the sub-channel program SACOS-PB was developed independently. As an example, the rectangle nine fuel rods construction was set, and its coolant temperature along the axial length was calculated. The results show that calculating results are good agreement with the reference results and the CFX calculating results. The three different constructions of the sub-channels were analyzed using SACOS-PB program, and the results show that the hexagon construction is the most suitable construction. The current research results establish a foundation for the further study. (authors)
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 47
- Journal Issue
- 1
- Journal Page Range
- p. 38-42
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 46131929
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BISMUTH; CONSTRUCTION; COOLANTS; FAST REACTORS; FUEL RODS; LEAD; LENGTH; LIQUID METALS; NUMERICAL ANALYSIS; S CODES; THERMAL HYDRAULICS
- Descriptors DEC
- COMPUTER CODES; DIMENSIONS; ELEMENTS; EPITHERMAL REACTORS; FLUID MECHANICS; FLUIDS; FUEL ELEMENTS; HYDRAULICS; LIQUIDS; MATHEMATICS; MECHANICS; METALS; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 10 figs., 6 refs.