Published August 1997 | Version v1
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Integrity: A semi-mechanistic model for stress corrosion cracking of fuel

  • 1. Atomic Energy of Canada Ltd., Mississauga, ON (Canada)
  • 2. Electric Power Development Co. Ltd., Tokyo (Japan)

Description

In this paper we describe the features, validation, and illustrative applications of a semi-mechanistic model, INTEGRITY, which calculates the probability of fuel defects due to stress corrosion cracking. The model expresses the defect probability in terms of fundamental parameters such as local stresses, local strains, and fission product concentration. The assessments of defect probability continue to reflect the influence of conventional parameters like ramped power, power-ramp, burnup and Canlub coating. In addition, the INTEGRITY model provides a mechanism to account for the impacts of additional factors involving detailed fuel design and reactor operation. Some examples of the latter include pellet density, pellet shape and size, sheath diameter and thickness, pellet/sheath clearance, coolant temperature and pressure, etc. The model has been fitted to a database of 554 power-ramp irradiations of CANDU fuel with and without Canlub. For this database the INTEGRITY model calculates 75 defects vs 75 actual defects. Similarly good agreements were noted in the different sub-groups of the data involving non-Canlub, thin-Canlub, and thick-Canlub fuel. Moreover, the shapes and the locations of the defect thresholds were consistent with all the above defects as well as with additional 14 ripple defects that were not in the above database. Two illustrative examples demonstrate how the defect thresholds are influenced by changes in the internal design of the fuel element and by extended burnup. (author). 19 refs, 7 figs

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Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting
Imprint Pagination
559 p.
Journal Page Range
p. 361-379.
ISSN
1011-4289
Report number
IAEA-TECDOC--957

Conference

Title
Technical committee meeting on water reactor fuel element modelling at high burnup and its experimental support.
Dates
19-23 Sep 1994.
Place
Windermere (United Kingdom).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
28068603
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; CANDU TYPE REACTORS; CRACKING; DEFECTS; DENSITY; FUEL ELEMENTS; FUEL PELLETS; MATHEMATICAL MODELS; PROBABILITY; SIZE; STRESS CORROSION; VALIDATION
Descriptors DEC
CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; HEAVY WATER MODERATED REACTORS; PHYSICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; PYROLYSIS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS

Optional Information