Assessment of post-LOCA long term cooling considering the in-vessel downstream effect

Author:

Amin Shah Asad Ullah,Bang Young Seok,Lee Joo-Seok

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference8 articles.

1. Bang, Y.S., Lee, Joo-Seok, 2016. Thermal-Hydraulic Modeling of In-core Blockage by Debris for Post-LOCA Long Term Core Cooling Phase, The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, Gyeongju.

2. Geelhood, K.J. et al., 2014. FRAPTRAN: A Computer Code for the Transient Analysis of Oxide Fuel Rods, NUREG/CR-7023. Pacific Northwest National Laboratory Richland.

3. MARS Code Manual, KAERI/TR-2811/2004;KAERI,2009

4. In-Vessel Downstream Effect Tests for Shin-Kori 3&4, APR1400-K-A-I (RA)-12003-P (R2);KHNP,2014

5. KHNP, 2015. In-Vessel Downstream Effect Evaluation of APR1400, APR1400-K-A-NR-14002-P, Rev. 2. Korea Hydro and Nuclear Power Co., Korea.

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