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Title: ARRC: A random ray neutron transport code for nuclear reactor simulation

Authors:
; ; ORCiD logo;
Publication Date:
Sponsoring Org.:
USDOE Office of Science (SC), Advanced Scientific Computing Research (ASCR) (SC-21)
OSTI Identifier:
1549043
Grant/Contract Number:  
AC02-06CH11357
Resource Type:
Publisher's Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Name: Annals of Nuclear Energy (Oxford) Journal Volume: 112 Journal Issue: C; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Country of Publication:
United Kingdom
Language:
English

Citation Formats

Tramm, John R., Smith, Kord S., Forget, Benoit, and Siegel, Andrew R. ARRC: A random ray neutron transport code for nuclear reactor simulation. United Kingdom: N. p., 2018. Web. doi:10.1016/j.anucene.2017.10.015.
Tramm, John R., Smith, Kord S., Forget, Benoit, & Siegel, Andrew R. ARRC: A random ray neutron transport code for nuclear reactor simulation. United Kingdom. doi:10.1016/j.anucene.2017.10.015.
Tramm, John R., Smith, Kord S., Forget, Benoit, and Siegel, Andrew R. Thu . "ARRC: A random ray neutron transport code for nuclear reactor simulation". United Kingdom. doi:10.1016/j.anucene.2017.10.015.
@article{osti_1549043,
title = {ARRC: A random ray neutron transport code for nuclear reactor simulation},
author = {Tramm, John R. and Smith, Kord S. and Forget, Benoit and Siegel, Andrew R.},
abstractNote = {},
doi = {10.1016/j.anucene.2017.10.015},
journal = {Annals of Nuclear Energy (Oxford)},
number = C,
volume = 112,
place = {United Kingdom},
year = {2018},
month = {2}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
DOI: 10.1016/j.anucene.2017.10.015

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