Numerical modeling of fuel rod transient response under out of pile test conditions. (May 2019)
- Record Type:
- Journal Article
- Title:
- Numerical modeling of fuel rod transient response under out of pile test conditions. (May 2019)
- Main Title:
- Numerical modeling of fuel rod transient response under out of pile test conditions
- Authors:
- Yadav, Ashwini Kumar
Shin, Chang-Hwan
Lee, Chan
Lee, Sung-Uk
Kim, Hyo Chan - Abstract:
- Abstract: As per revised Emergency core cooling system (ECCS) acceptance criteria, a precise prediction of fuel rod behavior is essential for realistic safety analysis of nuclear reactor. In this context, a one-dimensional code name 'TRAFR' (Transient Response Analysis of Fuel Rod) is developed to simulate the thermo-mechanical behavior of Zircaloy-4 cladding under transient conditions. The transient simulations for inert and oxidizing atmosphere were performed under out of pile test conditions and the predicted burst strains were in good agreement with the experiments conducted in past. Under inert atmosphere, the cladding rupture was delayed and burst strain was higher in all the phases due to the absence of oxidation kinetics. In the oxidizing atmosphere, the burst strain was considerably small at high temperature in mix phase (α+β) and β-phase due to increment in cladding strength and reduction in ductility. For the same internal pressure and clad surface boundary conditions, the temperature of failure was higher for oxidizing atmosphere due to heat generation by exothermic reactions at the surface of the cladding. The clad surface temperature rise rate decreased before the burst with increment in gap width between pellet and cladding owing to decrement in gap conductance. The code under-predicted the burst strain in the mix phase (α+β) and β-phase by 'Baker-Just' model. The reason for such deviation was abrupt parabolic oxide growth prediction with higher exothermicAbstract: As per revised Emergency core cooling system (ECCS) acceptance criteria, a precise prediction of fuel rod behavior is essential for realistic safety analysis of nuclear reactor. In this context, a one-dimensional code name 'TRAFR' (Transient Response Analysis of Fuel Rod) is developed to simulate the thermo-mechanical behavior of Zircaloy-4 cladding under transient conditions. The transient simulations for inert and oxidizing atmosphere were performed under out of pile test conditions and the predicted burst strains were in good agreement with the experiments conducted in past. Under inert atmosphere, the cladding rupture was delayed and burst strain was higher in all the phases due to the absence of oxidation kinetics. In the oxidizing atmosphere, the burst strain was considerably small at high temperature in mix phase (α+β) and β-phase due to increment in cladding strength and reduction in ductility. For the same internal pressure and clad surface boundary conditions, the temperature of failure was higher for oxidizing atmosphere due to heat generation by exothermic reactions at the surface of the cladding. The clad surface temperature rise rate decreased before the burst with increment in gap width between pellet and cladding owing to decrement in gap conductance. The code under-predicted the burst strain in the mix phase (α+β) and β-phase by 'Baker-Just' model. The reason for such deviation was abrupt parabolic oxide growth prediction with higher exothermic heat generation and subsequent faster reduction in cladding thickness which made 'Baker-Just' model approach more conservative than 'Cathcart-Pawel' model. Highlights: A fully-coupled 1-D code named 'TRAFR' is developed to access thermo-mechanical behavior of cladding. The effect of oxidation was significant at high temperature resulting into lower burst strains. The conservative approach of 'Baker-Just' model led to abrupt parabolic oxide growth prediction. In the absence of oxidation the cladding was able to sustain against internal stresses for longer duration. … (more)
- Is Part Of:
- Progress in nuclear energy. Volume 113(2019)
- Journal:
- Progress in nuclear energy
- Issue:
- Volume 113(2019)
- Issue Display:
- Volume 113, Issue 2019 (2019)
- Year:
- 2019
- Volume:
- 113
- Issue:
- 2019
- Issue Sort Value:
- 2019-0113-2019-0000
- Page Start:
- 62
- Page End:
- 73
- Publication Date:
- 2019-05
- Subjects:
- Loss of coolant accident -- Clad tube ballooning -- LOCA -- Nuclear fuel
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
333.7924 - Journal URLs:
- http://www.sciencedirect.com/science/journal/01491970 ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.pnucene.2019.01.014 ↗
- Languages:
- English
- ISSNs:
- 0149-1970
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 6870.542000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 9631.xml