Published April 2018
| Version v1
Journal article
Risks and analyses about fuel rod as being surrounded by concentric layers of oxide, crud and precipitate during the post-LOCA of CPR100
Creators
- 1. China Nuclear Power Technology Research Institute, Shenzhen (China)
Description
The risks about oxide, crud and chemical precipitate around the fuel rod during the post-LOCA of CPR1000 were analyzed. In an extreme condition, by using the steady-state thermal analysis module of ANSYS, based on the different thickness and the thermal conductivity of the fuel rod as being surrounded by concentric layers of chemical precipitate of AFA-3 G fuel assembly to analyses the effect on heat transfer. Under the conservative boundary conditions, the calculation results had showed that the maximum temperature of the surface of fuel rod cladding was 305.02℃, less than 426.7℃. In the extreme conditions, fuel rod thermal situation was still acceptable during the post-LOCA of CPR1000. (authors)
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 38
- Journal Issue
- 2
- Journal Page Range
- p. 313-317
- ISSN
- 0258-0918
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 55007003
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BOUNDARY CONDITIONS; CLADDING; FUEL ASSEMBLIES; FUEL RODS; HAZARDS; HEAT TRANSFER; LOSS OF COOLANT; OXIDES; PRECIPITATION; STEADY-STATE CONDITIONS; SURFACES; THERMAL ANALYSIS; THERMAL CONDUCTIVITY; THICKNESS
- Descriptors DEC
- ACCIDENTS; CHALCOGENIDES; DEPOSITION; DIMENSIONS; ENERGY TRANSFER; FUEL ELEMENTS; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; SEPARATION PROCESSES; SURFACE COATING; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- 9 figs., 3 tabs., 6 refs.