COMTA - a computer code for fuel mechanical and thermal analysis
- 1. Bhabha Atomic Research Centre, Bombay (India). Reactor Engineering Div.
Description
COMTA is a generalized computer code for integrity analysis of the free standing fuel cladding, with natural UO2 or mixed oxide fuel pellets. Thermal and Mechanical analysis is done simultaneously for any power history of the fuel pin. For analysis, the fuel cladding is assumed to be axisymmetric and is subjected to axisymmetric load due to contact pressure, gas pressure, coolant pressure and thermal loads. Axial variation of load is neglected and creep and plasticity are assumed to occur at constant volume. The pellet is assumed to be made of concentric annuli. The fission gas release integral is dependent on the temperature and the power produced in each annulus. To calculate the temperature distribution in the fuel pin, the variation of bulk coolant temperature is given as an input to the code. Gap conductance is calculated at every time step, considering fuel densification, fuel relocation and gap closure, filler gas dilution by released fission gas, gap closure by expansion and irradiation swelling. Overall gap conductance is contributed by heat transfer due to the three modes; conduction convection and radiation as per modified Ross and Stoute model. Equilibrium equations, compatibility equations, stress strain relationships (including thermal strains and permanent strains due to creep and plasticity) are used to obtain triaxial stresses and strains. Thermal strain is assumed to be zero at hot zero power conditions. The boundary conditions are obtained for radial stresses at outside and inside surfaces by making these equal to coolant pressure and internal pressure respectively. A multi-mechanism creep model which accounts for thermal and irradiation creep is used to calculate the overall creep rate. Effective plastic strain is a function of effective stress and material constants. (orig.)
Additional details
Publishing Information
- Publisher
- North-Holland Publishing Co.
- Imprint Place
- Amsterdam, Netherlands
- ISBN
- 0444 85359 6
- Imprint Title
- Structural mechanics in reactor technology. Transactions. Vol. C
- Journal Page Range
- p. C3/11 (1-8).
Conference
- Title
- 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2).
- Dates
- 9 - 21 Aug 1979.
- Place
- Berlin, Germany, F.R.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 12588853
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; FUEL CANS; STRESS ANALYSIS; THERMAL ANALYSIS
- Descriptors DEC
- COMPUTER CODES
Optional Information
- Secondary number(s)
- INKA-Conf--79-321-094.