Safety analyses of reactor VVER 1000-Reference-Cited by-同舟云学术

Safety analyses of reactor VVER 1000

Published:2017-09 Issue: Volume:127 Page:352-359
ISSN:1876-6102
Container-title:Energy Procedia
language:en
Short-container-title:Energy Procedia

Author:

Vojackova Jitka,Novotny Filip,Katovsky Karel

Publisher

Elsevier BV

Reference15 articles.

1. Todorova N., Taylor B., Ivanov K. Pressurised Water Reactor Main Steam Line Break (Mslb) Benchmark. NEA/NSC/DOC (2002)12.

2. VVER-1000 Coolant Transient Benchmark;Ivanov,2002

3. Akdeniz B., Ivanov k. N. Boiling Water Reactor Turbine Trip (Tt) Benchmark. ISBN 92-64-02331-3.

4. WEISS, F. P., MITTAG, S., Validation of coupled neutron-kinetic / thermal-hydraulic codes against transients measured in VVER reactors, Phare SRR-1/95: Final Technical Report FZR/SRR195/FIN2 1, Brussels, Belgium (2000).

5. Mittag, S., Grundmann, U. et al. Validation of coupled neutronic / thermal-hydraulic codes for VVER reactors Final report (FZR–408) Germany, (2004).

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