FINITE ELEMENT ANALYSIS OF AN EMPTY 37-ELEMENT CANDU® FUEL BUNDLE TO STUDY THE EFFECTS OF PRESSURE TUBE CREEP

Author:

Lee Kyuhwan1,Wowk Diane1,Chan Paul1

Affiliation:

1. Royal Military College of Canada, Kingston, ON K7K 7B4, Canada

Abstract

CANDU fuel bundles experience plastic deformations over time, and the horizontal configuration of the bundle in a crept pressure tube (PT) causes coolant to bypass the sagged lower half of the bundle. Bundle segments where the flow is limited may become more susceptible to dryout due to reactor aging. A finite element model of a 37-element fuel bundle was constructed using the commercial finite element software ANSYS to study the mechanical deformation behaviour of the bundle to maintain a coolable geometry. The main focus was on the contact between the fuel elements and between the fuel elements and PT. The complexity of the model due to all the contact pairs necessitated the use of high-powered computing hardware. Contact was demonstrated between the appendages, and sensitivity of the deformation to different boundary conditions (BC) was investigated. In particular, the radial position where the elements were welded to the endplate significantly impacted the magnitude of the element bowing. Expanding the PT up to 8% diametral creep demonstrated the proper functioning of the spacer pads (SP) and bearing pads in preventing sheath-to-sheath contact at the midplane and sheath-to-PT contact. However, the quarter plane was deemed to be the critical region due to the lack of SPs preventing excessive element bowing. This work has successfully illustrated the deformation of a CANDU fuel bundle, with contact, and its similarity with the bow profiles when compared with post-irradiation examination results and bundle heat-up tests.

Publisher

Canadian Nuclear Laboratories Limited

Subject

General Earth and Planetary Sciences,General Environmental Science

Reference6 articles.

1. B. Garland, 2014, The Essential CANDU, 46, UNENE, Hamilton, ON, Canada.

2. Canadian Nuclear Safety Commission (CNSC), 2006, G-144: Trip Parameter Acceptance Criteria for the Safety Analysis of CANDU Nuclear Power Plants, CNSC, Ottawa, ON, Canada.

3. In-reactor deformation of cold-worked Zr–2.5Nb pressure tubes

4. R. Soni, 2017, “Analyzing the 3-Dimensional Deformation Behaviour of an Empty CANDU Fuel Bundle Using the Finite Element Method,” Master’s Thesis, Royal Military College of Canada (RMC), Kingston, ON, Canada.

5. C. Krasnaj, 2015, “A Solid Element Approach to Analyzing CANDU Fuel Element Behaviour under Post-Dryout Heat Transfer Conditions,” Master’s Thesis, Royal Military College of Canada (RMC), Kingston, ON, Canada.

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