Integrity: A semi-mechanistic model for stress corrosion cracking of fuel
Creators
- 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
Files
28068603.pdf
Files
(582.8 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:a2bec669d7bfd37a265f285628b61dc6
|
582.8 kB | Preview Download |
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