Study on response characteristic of CiADS sub-critical reactor fuel cladding under beam transient
- 1. University of Chinese Academy of Sciences, Beijing (China)
- 2. Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou (China)
Description
The point kinetic model and the heat transfer model of the reactor system analysis code RELAP 5 MOD 4.0 were modified, which provided the capacity to simulate the dynamic characteristics of the liquid lead-bismuth cooled sub-critical reactor. The response characteristics of the fuel rods in the sub-critical reactor of China Initiative Accelerator Driven System (CiADS) under beam transient were simulated by the improved code RELAP 5 MOD 4.0. The variation of stress of the fuel cladding in CiADS under beam transient was analyzed by ANSYS 17.0 code. The results show that the shorter the time of beam trip the slower the temperature of the fuel rod recovery. The fuel cladding will not melt in the possible overpower event of the beam. The change of temperature difference between inner wall and outer wall of fuel cladding is the main factor of stress variation. The beam transient will not cause stress damage to the fuel cladding in CiADS sub-critical reactor. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 52
- Journal Issue
- 5
- Journal Page Range
- p. 931-936
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 55027389
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCELERATOR-DRIVEN SUBCRITICAL SYSTEMS; BEAMS; CHINA; FUEL CANS; FUEL RODS; HEAT TRANSFER; KINETICS; SIMULATION; STRESSES; SYSTEMS ANALYSIS; TRANSIENTS; WALLS
- Descriptors DEC
- ASIA; ENERGY TRANSFER; EXPERIMENTAL REACTORS; FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SUBCRITICAL ASSEMBLIES
Optional Information
- Notes
- 9 figs., 16 refs.; http://dx.doi.org/10.7538/yzk.2018.52.05.0931