Bulging of pressure tubes at hot spots under LOCA conditions
- 1. Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)
- 2. Atomic Energy of Canada Limited, Pinawa, Manitoba (Canada)
Description
During certain postulated loss-of-coolant accidents (LOCA) in a CANDU reactor, some fuel channels can become highly voided within a very short time. Although the pressure tubes are heated mainly by convection and thermal radiation during the LOCA transient, additional heat flow occurs through the bearing pads that are in contact with the pressure tribe. This contact can lead to local hot spots and associated thermal stresses in the pressure tube wall. The two factors that affects the behavior of the pressure tubes during LOCA conditions are the internal pressure and the local heating. Although the effect of internal pressure and of axially uniform temperature has been studied elsewhere, the effect of the local heating on the pressure tube behavior has not been modelled before. This paper shows that the bulging of a pressure tube at a hot spot is the result of the thermal stresses that are developed in a pressure tube during a LOCA transient. To isolate the local heating effect from the internal pressure, a series of single-effect experiments was performed. In these experiments, sections of a CANDU pressure tube were subjected to local heating only. The thermal profile and the local deformation were measured function of time. To quantify the effect of the thermal stresses on the bulging of pressure tubes at hot spots and to develop numerical tools that can predict such bulging, finite element analyses were performed rising the ABAQUS finite element computer code. Use of the measured thermal profiles in the ABAQUS finite element analysis, resulted in very good agreement between the predicted and measured displacements. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-47-X
- Imprint Title
- Simulation methods in nuclear engineering
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.2) [21 p.]
Conference
- Title
- 5. International conference on simulation methods in nuclear engineering
- Dates
- 8-11 Sep 1996
- Place
- Montreal, PQ (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 33018551
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; CANDU TYPE REACTORS; FINITE ELEMENT METHOD; FUEL CHANNELS; HOT SPOTS; LOSS OF COOLANT; PRESSURE TUBES; THERMAL CONDUCTIVITY; THERMAL STRESSES; VOID COEFFICIENT
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; HEAVY WATER MODERATED REACTORS; NUMERICAL SOLUTION; PHYSICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTIVITY COEFFICIENTS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; STRESSES; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TUBES
Optional Information
- Notes
- 9 refs., 9 figs.