Steady State and Transient Thermalhydraulic Analysis of PHWR Using COBRA-3C/RERTR
Recommended Citation
A. Hussain et al., "Steady State and Transient Thermalhydraulic Analysis of PHWR Using COBRA-3C/RERTR," Transactions of the American Nuclear Society, American Nuclear Society (ANS), Jan 2013.
Meeting Name
2013 Winter Meeting on Transactions and Embedded Topical Meetings: Risk Management for Complex Socio-Technical Systems, 2nd ANS SMR 2013 Conference, Nuclear Nonproliferation - 1st Fission to the Future
Department(s)
Nuclear Engineering and Radiation Science
International Standard Serial Number (ISSN)
0003-018X
Document Type
Article - Conference proceedings
Document Version
Citation
File Type
text
Language(s)
English
Rights
© 2013 American Nuclear Society (ANS), All rights reserved.
Publication Date
01 Jan 2013