Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding

Cheng, Bo; Kim, Young-Jin; Chou, Peter

doi:10.1016/j.net.2015.12.003

Title: Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding

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Authors:: Cheng, Bo; Kim, Young-Jin; Chou, Peter

Publication Date:: Mon Feb 01 00:00:00 EST 2016

Sponsoring Org.:: USDOE

OSTI Identifier:: 1253199

Resource Type:: Published Article

Journal Name:: Nuclear Engineering and Technology

Additional Journal Information:: Journal Name: Nuclear Engineering and Technology Journal Volume: 48 Journal Issue: 1; Journal ID: ISSN 1738-5733

Publisher:: Elsevier

Country of Publication:: Korea, Republic of

Language:: English

Citation Formats


                    Cheng, Bo, Kim, Young-Jin, and Chou, Peter. Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding.  Korea, Republic of: N. p., 2016. 
Web.  doi:10.1016/j.net.2015.12.003.

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                    Cheng, Bo, Kim, Young-Jin, & Chou, Peter. Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding.  Korea, Republic of.  https://doi.org/10.1016/j.net.2015.12.003

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                    Cheng, Bo, Kim, Young-Jin, and Chou, Peter. Mon .  
"Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding".  Korea, Republic of.  https://doi.org/10.1016/j.net.2015.12.003.

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@article{osti_1253199,

  title        = {Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding},

  author       = {Cheng, Bo and Kim, Young-Jin and Chou, Peter},

  abstractNote = {},

  doi          = {10.1016/j.net.2015.12.003},

  journal      = {Nuclear Engineering and Technology},

  number       = 1,

  volume       = 48,

  place        = {Korea, Republic of},

  year         = {Mon Feb 01 00:00:00 EST 2016},

  month        = {Mon Feb 01 00:00:00 EST 2016}

}

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