Benchmark and demonstration of the CHD code for transient analysis of fast reactor systems

Author:

Hellesen C.ORCID,Qvist S.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference18 articles.

1. Advanced Thermohydraulic Simulation Code for Transients in LMFBRs (SSC-L Code);Agrawal,1978

2. ANS, 2014, ANSI/ANS-5.1-2014, Decay Heat Power in Light Water Reactors.

3. The SAS4A/ SASSYS-1 Safety Analysis Code System, ANL/NE-12/4;Argonne National Laboratory, Nuclear Engineering Division,2011

4. Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow;Chenu;Nucl. Eng. Des.,2011

5. Darmet, G., Massara, S., 2012. Dynamical analysis of innovative core designs facing unprotected transients with the MAT5-DYN code. In: Proceedings of ICAPP 2012, Paper 12245.

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