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Integrity: A semi-mechanistic model for stress corrosion cracking of fuel

Abstract

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  More>>
Authors:
Tayal, M; Hallgrimson, K; Macquarrie, J; Alavi, P; [1]  Sato, S; Kinoshita, Y; Nishimura, T [2] 
  1. Atomic Energy of Canada Ltd., Mississauga, ON (Canada)
  2. Electric Power Development Co. Ltd., Tokyo (Japan)
Publication Date:
Aug 01, 1997
Product Type:
Conference
Report Number:
IAEA-TECDOC-957; CONF-9409411-
Reference Number:
SCA: 210400; PA: AIX-28:068603; EDB-97:129998; SN: 97001863139
Resource Relation:
Conference: IAEA technical committee meeting on water reactor fuel element modelling at high burnup and its experimental support, Windermere (United Kingdom), 19-23 Sep 1994; Other Information: PBD: Aug 1997; Related Information: Is Part Of Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting; PB: 559 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; CRACKING; STRESS CORROSION; FUEL ELEMENTS; BURNUP; CANDU TYPE REACTORS; DEFECTS; DENSITY; FUEL PELLETS; MATHEMATICAL MODELS; PROBABILITY; SIZE; VALIDATION
OSTI ID:
534376
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE98602336; TRN: XA9744811068603
Availability:
INIS; OSTI as DE98602336
Submitting Site:
INIS
Size:
pp. 361-379
Announcement Date:
Oct 31, 1997

Citation Formats

Tayal, M, Hallgrimson, K, Macquarrie, J, Alavi, P, Sato, S, Kinoshita, Y, and Nishimura, T. Integrity: A semi-mechanistic model for stress corrosion cracking of fuel. IAEA: N. p., 1997. Web.
Tayal, M, Hallgrimson, K, Macquarrie, J, Alavi, P, Sato, S, Kinoshita, Y, & Nishimura, T. Integrity: A semi-mechanistic model for stress corrosion cracking of fuel. IAEA.
Tayal, M, Hallgrimson, K, Macquarrie, J, Alavi, P, Sato, S, Kinoshita, Y, and Nishimura, T. 1997. "Integrity: A semi-mechanistic model for stress corrosion cracking of fuel." IAEA.
@misc{etde_534376,
title = {Integrity: A semi-mechanistic model for stress corrosion cracking of fuel}
author = {Tayal, M, Hallgrimson, K, Macquarrie, J, Alavi, P, Sato, S, Kinoshita, Y, and Nishimura, T}
abstractNote = {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.}
place = {IAEA}
year = {1997}
month = {Aug}
}