Modeling of Microstructure Evolution in Austenitic Stainless Steels Irradiated Under Light Water Reactor Conditions

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A model for the development of microstructure during irradiation in fast reactors has been adapted for light water reactor (LWR) irradiation conditions (275 {approximately} 325 C, up to {approximately}10 dpa). The original model was based on the rate-theory, and included descriptions of the evolution of both dislocation loops and cavities. The model was modified by introducing in-cascade interstitial clustering, a term to account for the dose dependence of this clustering, and mobility of interstitial clusters. The purpose of this work was to understand microstructural development under LWR irradiation with a focus on loop nucleation and saturation of loop density. It ... continued below

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6 p.

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Gan, J.; Stoller, R.E. & Was, G.S. November 30, 1998.

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Description

A model for the development of microstructure during irradiation in fast reactors has been adapted for light water reactor (LWR) irradiation conditions (275 {approximately} 325 C, up to {approximately}10 dpa). The original model was based on the rate-theory, and included descriptions of the evolution of both dislocation loops and cavities. The model was modified by introducing in-cascade interstitial clustering, a term to account for the dose dependence of this clustering, and mobility of interstitial clusters. The purpose of this work was to understand microstructural development under LWR irradiation with a focus on loop nucleation and saturation of loop density. It was demonstrated that in-cascade interstitial clustering dominates loop nucleation in neutron irradiation in LWRS. Furthermore it was shown that the dose dependence of in-cascade interstitial clustering is needed to account for saturation behavior as commonly observed. Both quasi-steady-state (QSS) and non-steady-state (NSS) solutions to the rate equations were obtained. The difference between QSS and NSS treatments in the calculation of defect concentration is reduced at LWR temperature when in-cascade interstitial clustering dominates loop nucleation. The mobility of interstitial clusters was also investigated and its impact on loop density is to reduce the nucleation term. The ultimate goal of this study is to combine the evolution of microstructure and microchemistry together to account for the radiation damage in austenitic stainless steels.

Physical Description

6 p.

Notes

INIS; OSTI as DE00003656

Medium: P; Size: 6 pages

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  • Fall Meeting of the Materials Research Society, Boston, MA (US), 11/30/1999--12/04/1999

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  • Report No.: ORNL/CP-101210
  • Report No.: KC 02 01 04 0
  • Report No.: AT 60 20 00 0
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 3656
  • Archival Resource Key: ark:/67531/metadc684734

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  • November 30, 1998

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  • July 25, 2015, 2:20 a.m.

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  • April 11, 2017, 2:36 p.m.

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Gan, J.; Stoller, R.E. & Was, G.S. Modeling of Microstructure Evolution in Austenitic Stainless Steels Irradiated Under Light Water Reactor Conditions, article, November 30, 1998; Tennessee. (digital.library.unt.edu/ark:/67531/metadc684734/: accessed September 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.