Stress state dependence of in-reactor creep and swelling

Hall, M.M.

doi:10.1016/j.jnucmat.2009.10.063

Cited by 12 publications

(16 citation statements)

References 19 publications

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“…(6) and (7) of [1] are correct as published and the data reported in ''Stress state dependence of in-reactor creep and swelling. Part II: experimental results'' [2] were fitted to these equations. However, errors were made in recasting these equations and fitting parameters in forms that can be related to the empirical equations that have been used extensively in analysis and reporting of irradiation creep and swelling data.…”

mentioning

confidence: 69%

“…Eqs. (6) and (7) of [1] are correct as published and the data reported in ''Stress state dependence of in-reactor creep and swelling. Part II: experimental results'' [2] were fitted to these equations.…”

mentioning

confidence: 74%

“…Part I: continuum plasticity model'' [1], multiaxial equations were developed for components of in-reactor creep and swelling; stress-free swelling, stress-affected swelling, and swelling-dependent creep. The swelling-independent creep component was added by adopting a conventional power-law creep expression.…”

mentioning

confidence: 99%

“…Errors in recasting the equations derived in [1], in terms of the above equations, stem from the fact that Eq. (10) of [1] is missing the factor of 3/2 that appears in Eq.…”

mentioning

confidence: 99%

See 3 more Smart Citations

Errata to: “Stress state dependence of in-reactor creep and swelling. Part I: continuum plasticity model”, Journal of Nuclear Materials 396 (2010) 112–118 and “Stress state dependence of in-reactor creep and swelling. Part II: experimental results”, Journal of Nuclear Materials 396 (2010) 119–129

Hall¹

2011

Journal of Nuclear Materials

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mentioning

confidence: 69%

mentioning

confidence: 74%

mentioning

confidence: 99%

“…Errors in recasting the equations derived in [1], in terms of the above equations, stem from the fact that Eq. (10) of [1] is missing the factor of 3/2 that appears in Eq.…”

mentioning

confidence: 99%

See 2 more Smart Citations

Errata to: “Stress state dependence of in-reactor creep and swelling. Part I: continuum plasticity model”, Journal of Nuclear Materials 396 (2010) 112–118 and “Stress state dependence of in-reactor creep and swelling. Part II: experimental results”, Journal of Nuclear Materials 396 (2010) 119–129

Hall¹

2011

Journal of Nuclear Materials

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“…Additionally, in the low stress range, a power law formulation of irradiation creep rate is typically characterized by a stress exponent of 1, diffusional creep being the dominating mechanism (NabarroHerring or Coble creep). However, at large stresses, the stress exponent of 4-5 and as high as 7 have been documented for various Uranium alloys [46,[50][51][52][53][54][55]. This mechanism is attributed to dislocation creep.…”

Section: Model and Experiments Comparisonmentioning

confidence: 99%

Evaluation of U10Mo Fuel Plate Irradiation Behavior via Numerical and Experimental Benchmarking

Miller

Ozaltun

2012

Volume 6: Energy, Parts a and B

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This article analyzes dimensional changes due to irradiation of monolithic plate-type nuclear fuel and compares results with finite element analysis of the plates during fabrication and irradiation. Monolithic fuel plates tested in the Advanced Test Reactor (ATR) at Idaho National Lab (INL) are being used to benchmark the performance of proposed fuel for several high power research reactors. Post-irradiation metallographic images of plates sectioned at the mid-plane were analyzed to determine dimensional changes of the fuel and the cladding response. A constitutive model of the fabrication process and irradiation behavior of the tested plates was developed using the general purpose commercial finite element analysis package, ABAQUS. Using calculated burn-up profiles of irradiated plates to model the power distribution and including irradiation behaviors such as swelling and irradiation enhanced creep, model simulations allow analysis of plate parameters that are either impossible or infeasible in an experimental setting. The development and progression of fabrication induced stress concentrations at the plate edges was of primary interest, as these locations have a unique stress profile during irradiation. Additionally, comparison between 2D and 3D models was performed to optimize analysis methodology. In particular, the ability of 2D and 3D models to account for out of plane stresses which result in 3-dimensional creep behavior that is a product of these components. Results show that assumptions made in 2D models for the out-of-plane stresses and strains cannot capture the 3-dimensional physics accurately and thus 2D approximations are not representative. Stress-strain fields are dependent on plate geometry and irradiation conditions, thus, if stress based criteria is used to predict plate behavior (as opposed to material impurities, fine micro-structural defects, or sharp power gradients), unique 3D finite element formulation for each plate is required.

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Analysis of the influence of type of stress state on radiation swelling and radiation creep of austenitic steels

2012

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Stress state dependence of in-reactor creep and swelling

Cited by 12 publications

References 19 publications

Evaluation of U10Mo Fuel Plate Irradiation Behavior via Numerical and Experimental Benchmarking

Analysis of the influence of type of stress state on radiation swelling and radiation creep of austenitic steels

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