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Title: Study of High Fluence Radiation-induced Swelling and Hardening under Light Water Reactor Conditions

Abstract

This report documents a comprehensive model that has been developed to enable simulations of microstructural evolution under the irradiation conditions typical of light water reactor (LWR) internal components. The model, which accounts cascade production of point defects and vacancy, interstitial faulted dislocation loops, interstitial clusters migrating one-dimensionally and the evolution of the network dislocation structure, has been parameterized to account damage accumulation in austenitic stainless steels. Nucleation and growth of an ensemble of cavities is based on accounting the residual and produced by irradiation He atoms and existence of the dislocation and production biases. Additional applications and potential future developments for the model are also discussed.

Authors:
 [1];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1360055
Report Number(s):
ORNL/TM-2016/549
RC0304000; NERC006; M2LW-16OR0402042
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats

Golubov, Stanislav I., Barashev, Alexander V., and Stoller, Roger E. Study of High Fluence Radiation-induced Swelling and Hardening under Light Water Reactor Conditions. United States: N. p., 2016. Web. doi:10.2172/1360055.
Golubov, Stanislav I., Barashev, Alexander V., & Stoller, Roger E. Study of High Fluence Radiation-induced Swelling and Hardening under Light Water Reactor Conditions. United States. doi:10.2172/1360055.
Golubov, Stanislav I., Barashev, Alexander V., and Stoller, Roger E. Thu . "Study of High Fluence Radiation-induced Swelling and Hardening under Light Water Reactor Conditions". United States. doi:10.2172/1360055. https://www.osti.gov/servlets/purl/1360055.
@article{osti_1360055,
title = {Study of High Fluence Radiation-induced Swelling and Hardening under Light Water Reactor Conditions},
author = {Golubov, Stanislav I. and Barashev, Alexander V. and Stoller, Roger E.},
abstractNote = {This report documents a comprehensive model that has been developed to enable simulations of microstructural evolution under the irradiation conditions typical of light water reactor (LWR) internal components. The model, which accounts cascade production of point defects and vacancy, interstitial faulted dislocation loops, interstitial clusters migrating one-dimensionally and the evolution of the network dislocation structure, has been parameterized to account damage accumulation in austenitic stainless steels. Nucleation and growth of an ensemble of cavities is based on accounting the residual and produced by irradiation He atoms and existence of the dislocation and production biases. Additional applications and potential future developments for the model are also discussed.},
doi = {10.2172/1360055},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Sep 01 00:00:00 EDT 2016},
month = {Thu Sep 01 00:00:00 EDT 2016}
}

Technical Report:

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