Correlative Microscopy of Neutron-Irradiated Materials

Briggs, Samuel A.; Sridharan, Kumar; Field, Kevin G.

Title: Correlative Microscopy of Neutron-Irradiated Materials

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Abstract

A nuclear reactor core is a highly demanding environment that presents several unique challenges for materials performance. Materials in modern light water reactor (LWR) cores must survive several decades in high-temperature (300-350°C) aqueous corrosion conditions while being subject to large amounts of high-energy neutron irradiation. Next-generation reactor designs seek to use more corrosive coolants (e.g., molten salts) and even greater temperatures and neutron doses. The high amounts of disorder and unique crystallographic defects and microchemical segregation effects induced by radiation inevitably lead to property degradation of materials. Thus, maintaining structural integrity and safety margins over the course of the reactor's service life thus necessitates the ability to understand and predict these degradation phenomena in order to develop new, radiation-tolerant materials that can maintain the required performance in these extreme conditions.

Authors:

Briggs, Samuel A. ^[1]; Sridharan, Kumar ^[1]; Field, Kevin G. ^[2]

Univ. of Wisconsin, Madison, WI (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Nuclear Materials Science and Technology (NMST) Group

Publication Date:: Sat Dec 31 00:00:00 EST 2016

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Wisconsin, Madison, WI (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5); USDOE Office of Science (SC), Basic Energy Sciences (BES)

OSTI Identifier:: 1340452

Grant/Contract Number:: AC05-00OR22725; AC07-05ID14517

Resource Type:: Accepted Manuscript

Journal Name:: Advanced Materials and Processes

Additional Journal Information:: Journal Volume: 174; Journal Issue: 10; Journal ID: ISSN 0882-7958

Publisher:: ASM International

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE

Citation Formats


                    Briggs, Samuel A., Sridharan, Kumar, and Field, Kevin G. Correlative Microscopy of Neutron-Irradiated Materials.  United States: N. p., 2016. 
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                    Briggs, Samuel A., Sridharan, Kumar, & Field, Kevin G. Correlative Microscopy of Neutron-Irradiated Materials.  United States.

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                    Briggs, Samuel A., Sridharan, Kumar, and Field, Kevin G. Sat .  
"Correlative Microscopy of Neutron-Irradiated Materials".  United States.  https://www.osti.gov/servlets/purl/1340452.

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@article{osti_1340452,

  title        = {Correlative Microscopy of Neutron-Irradiated Materials},

  author       = {Briggs, Samuel A. and Sridharan, Kumar and Field, Kevin G.},

  abstractNote = {A nuclear reactor core is a highly demanding environment that presents several unique challenges for materials performance. Materials in modern light water reactor (LWR) cores must survive several decades in high-temperature (300-350°C) aqueous corrosion conditions while being subject to large amounts of high-energy neutron irradiation. Next-generation reactor designs seek to use more corrosive coolants (e.g., molten salts) and even greater temperatures and neutron doses. The high amounts of disorder and unique crystallographic defects and microchemical segregation effects induced by radiation inevitably lead to property degradation of materials. Thus, maintaining structural integrity and safety margins over the course of the reactor's service life thus necessitates the ability to understand and predict these degradation phenomena in order to develop new, radiation-tolerant materials that can maintain the required performance in these extreme conditions.},

  doi          = {},

  journal      = {Advanced Materials and Processes},

  number       = 10,

  volume       = 174,

  place        = {United States},

  year         = {Sat Dec 31 00:00:00 EST 2016},

  month        = {Sat Dec 31 00:00:00 EST 2016}

}

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