Development of a novel 1D coupled neutronics/thermal-hydraulics code and its verification on PWR rod ejection accident benchmark

Author:

Song HongbingORCID,Luo Run,Wan Jiashuang,Li Sha,Zhao Fuyu

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference46 articles.

1. A Jacobian-free Newton–Krylov method for thermalhydraulics simulations;Ashrafizadeh;Int. J. Numer. Methods Fluids,2015

2. Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR;Chaudri;Ann. Nucl. Energy,2012

3. Reactor axial power distribution control for PWR nuclear power plant;Cheng;Nucl. Power Eng.,1992

4. Homogenization and function of one-dimensional cross sections for RETRAN;Cronin;Nucl. Technol.,1992

5. A transverse buckling based method in core neutronics models equivalence;Dall’Osso;Ann. Nucl. Energy,2002

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