Comprehensive neutronic modeling of slug flow by Monte Carlo technique

Author:

Türkmen Mehmet,Tiftikci Ali

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference41 articles.

1. GE Hitachi Nuclear Energy, 2014. ESBWR Design Control Document Tier 2, Chapter 4: Reactor. 26A6642AP Revision 10. GE-Hitachi Nuclear Energy Americas LLC, USA (2014).

2. GE Hitachi Nuclear Energy, 2019. ABWR Design Control Document Tier 2, Chapter 4: Reactor. 25A5675AF Revision 7. GE-Hitachi Nuclear Energy Americas LLC, USA (2019).

3. Marshall, W.B.J., Ade, B.J., Bowman, S., Martinez-Gonzalez, J.S., 2016. Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit. NUREG/CR-7224 (ORNL/TM-2015/544), prepared for the US Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn, NUREG/CR-7224, ORNL/TM-2015/544.

4. Validation of interfacial area concentration model for simulating bubbly and cap/slug flow behaviors in large diameter pipes using LSTF, ATLAS, and horizontal pipe experiment data;Heo;Prog. Nucl. Energy,2020

5. Modelling of a Nordic BWR containment and suppression pool behavior during a LOCA with GOTHIC 8.1;Estévez-Albuja;Ann. Nucl. Energy,2020

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