Modelling transient two-dimensional non-linear temperatures in nuclear fuel using the FEAT code
- 1. Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)
- 2. Ryerson Polytechnic Univ., Dept. of Mechanical Engineering, Toronto, Ontario (Canada)
Description
A capability to model transient two-dimensional heat conduction has been added to the FEAT code, and is described in this paper. Results from the test cases show excellent agreement between FEAT calculations and corresponding analytical solutions. An illustrative example discusses the transient temperature in the pellet during a hypothetical loss-of-coolant accident in a CANDU 9 reactor. Two-dimensional calculations are performed to account for the effects of end-flux peaking and heat transfer through the endcaps. The case studies have shown that the net effect is to increase the peak pellet temperature by about 176 deg C, compared to the one dimensional situation of no end-flux peaking and no axial heat transfer through the endcap. Nevertheless, the peak pellet temperature of 2154 deg C is well below 2840 deg C , the melting point of UO2. (author)
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Additional details
Publishing Information
- ISBN
- 0-919784-50-X
- Imprint Title
- Proceedings of the fifth international conference on CANDU fuel. V.1,2
- Imprint Pagination
- [923 p.]
- Journal Page Range
- (v.1) p. 351-362
- Report number
- INIS-CA--0072
Conference
- Title
- 5. International conference on CANDU fuel
- Dates
- 21-25 Sep 1997
- Place
- Toronto, ON (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 31006107
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; F CODES; FINITE ELEMENT METHOD; FUEL PELLETS; HEAT TRANSFER; LOSS OF COOLANT; NUCLEAR FUELS; THERMAL CONDUCTIVITY; TRANSIENTS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; ENERGY SOURCES; ENERGY TRANSFER; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; NUMERICAL SOLUTION; PHYSICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- 9 refs., 8 figs.