Enhancement of Safety Analysis Capability for a CANDU-6 Reactor Using RELAP-CANDU/SCAN Coupled Code System
Author:
Affiliation:
1. Korea Institute of Nuclear Safety, Regulatory Research Division P.O. Box 114, Yusung, Taejon 305-600, Republic of Korea
2. Seoul National University, Nuclear Engineering Department, San 56-1, Shinlim-dong Kwanak-Gu, Seoul, Republic of Korea
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT06-A3782
Reference2 articles.
1. RELAP5 Prediction of Transient Tests in the RD-14 Test Facility
2. Unified Nodal Method Formulation for Analytic Function Expansion Nodal Method Solution to Two-Group Diffusion Equations in Rectangular Geometry
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