Uncertainty analysis of Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) using coupled DAKOTA with RELAP-3D method
Journal Article
·
· Nuclear Engineering and Design
Not Available
- Sponsoring Organization:
- USDOE
- OSTI ID:
- 1549221
- Journal Information:
- Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: C Vol. 324; ISSN 0029-5493
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- Netherlands
- Language:
- English
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