Published 1995 | Version v1
Miscellaneous Open

Thermally-induced bowing of CANDU fuel elements

  • 1. Korea Atomic Energy Research Inst., Taejon City (Korea, Republic of)

Description

Considering only the thermally-induced bending moments which are generated both within the sheath and between the fuel and sheath by an asymmetric temperature distribution with respect to the axis of an element, a generalized and explicit analytical formula for the thermally-induced bending is developed in this paper, based on the cases of 1) the bending of an empty tube treated by neglecting of the fuel/sheath mechanical interaction and 2) the fuel/sheath interaction due to the pellet and sheath temperature variations. In each of the cases, the temperature asymmetries in sheath are modelled to be caused by the combined effects of (i) non-uniform coolant temperature due to imperfect coolant mixing, (ii) variable sheath/coolant heat transfer coefficient, (iii) asymmetric heat generation due to neutron flux gradients across an element and so as to inclusively cover the uniform temperature distributions within the fuel and sheath with respect to the axial centerline. Investigating the relative importance of the various parameters affecting fuel element bowing, the element bowing is found to be greatly affected with the variations of element length, sheath diameter, pellet/sheath mechanical interaction and neutron flux depression factors, pellet thermal expansion coefficient, pellet/sheath heat transfer coefficient in comparison with those of other parameters such as sheath thickness, film heat transfer coefficient, sheath thermal expansion coefficient, and sheath and pellet thermal conductivities. Also, the element bowing of the standard 37-element bundle and CANFLEX 43-element bundle for the use in CANDU-6 reactors was analyzed with the formula, which could help to demonstrate the integrity of the fuel. All the required input data for the analyses were generated in terms of the reactor operation conditions on the reactor physics, thermal hydraulics and fuel performance by using various CANDU computer codes. The analysis results indicate that the CANFLEX 43-element bundle shows more desirable element bowing behaviours than the standard 37-element bundle. (author)

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Part of:
Conference proceedings of the 4. international conference on CANDU fuel. V. 1,2

Additional details

Publishing Information

ISBN
0-919784-53-4
Imprint Title
Conference proceedings of the 4. international conference on CANDU fuel. V. 1,2
Imprint Pagination
830 p.
Journal Page Range
v. 2 [18 p.]
Report number
INIS-CA--0069(v.1,2)

Conference

Title
safe, reliable, economical
Acronym
CANDU fuel
Dates
1-4 Oct 1995
Place
Pembroke, ON (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
30000513
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL CANS; FUEL ELEMENT CLUSTERS; FUEL INTEGRITY; FUEL PELLETS; NEUTRON FLUX; SPENT FUEL ELEMENTS; THERMAL FATIGUE; THERMAL STRESSES
Descriptors DEC
FATIGUE; FUEL ASSEMBLIES; FUEL ELEMENTS; MECHANICAL PROPERTIES; RADIATION FLUX; REACTOR COMPONENTS; STRESSES

Optional Information

Notes
12 refs., 1 tab., 7 figs.