Thermal safety characteristics analysis of helium xenon gas cooled small reactor system under LOCA accidents

Author:

Xianbo Wang,Hui Bao,Youyou Tian,Lin Xie,Fulong Zhao,Sichao Tan,Ruifeng Tian

Publisher

Elsevier BV

Reference39 articles.

1. Integrated Ananlysis for a Small Break LOCA in the IRIS Reactor Using MELCOR and RELAP5 Codes: 5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids;Alessandro,2004

2. The Investigation of Nonavailability of Passive Safety Systems Effects on Small Break LOCA Sequence in AP1000 Using RELAP5 MOD 4.0[J];Anwar,2016

3. Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design;Bae;Nucl. Eng. Technol.,2017

4. Transition from depressurization to long term cooling in AP600 scaled integral test facilities[J];Bessette;Nucl. Eng. Des.,1999

5. Boyack, B.E., Lime, J.F. Analysis of an AP600 intermediate-size loss-of-coolant accident[C]. 7th international topical meeting on nuclear reactor thermal-hydraulics (NURETH-7), New York, USA, Sep 10-15, 1995. https://doi.org/10.2172/107770.

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