PWR reflood experiments using full length bundles of rods with zircaloy claddings and alumina pellets

Author:

Ihle P.,Rust K.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference21 articles.

1. Blowdown/reflood tests with nuclear heated rods (IFA-511.2);Vitanza;OECD Halden Reactor Project, HPR 248,1980

2. Blowdown/reflood tests with SEMISCALE heaters (IF-511.3, Data Collection);Johnsen;OECD Halden Reactor Project, HWR 17,1981

3. Results of LOCA tests with SEMISCALE heaters (IFA-511.5);Johnsen;OECD Halden Reactor Project, HPR 313,1984

4. Results of blowdown/reflood tests with REBEKA electric simulators (IFA-511.4, Cycle 2);Vitanza;OECD Halden Reactor Project, HWR 85,1983

5. The quenching of irradiated fuel pins;Pigott;Nucl. Engrg. Des.,1975

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1. Experimental investigation of quench front propagation during reflooding in 5 × 5 rod bundle channel with axial uniform power distribution;Annals of Nuclear Energy;2024-10

2. Fractional scaling analysis of cladding temperature in large break loss of coolant accident;Nuclear Engineering and Design;2024-07

3. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

4. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

5. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

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