Preliminary Analysis of Unprotected Transients in the VTR
Author:
Affiliation:
1. Argonne National Laboratory, Nuclear Science and Engineering Division, 9700 S Cass Ave, Argonne, Illinois 60439
Funder
U.S. Department of Energy
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2021.2009982
Reference7 articles.
1. Versatile Test Reactor Conceptual Core Design
2. The SAS4A/SASSYS-1 Safety Analysis Code System, Version 5
3. Modeling of Safety Basis Events in the VTR
4. NEI, “Risk-Informed Performance-Based Guidance for Non-Light Water Reactor Licensing Basis Development,” Nuclear Energy Institute 18-04 Rev 1 (Aug 2019).
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