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

Authors:
; ;
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1253199
Resource Type:
Published Article
Journal Name:
Nuclear Engineering and Technology
Additional Journal Information:
Journal Volume: 48; Journal Issue: 1; Related Information: CHORUS Timestamp: 2018-09-16 10:51:25; 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.
Cheng, Bo, Kim, Young-Jin, & Chou, Peter. Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding. Korea, Republic of. doi:10.1016/j.net.2015.12.003.
Cheng, Bo, Kim, Young-Jin, and Chou, Peter. Mon . "Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding". Korea, Republic of. doi:10.1016/j.net.2015.12.003.
@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 = {2016},
month = {2}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
DOI: 10.1016/j.net.2015.12.003

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Cited by: 9 works
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