International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)

Session

6.11 IAEA Benchmark on EBR-II Shutdown Heat Removal Tests

26 Jun 2017, 15:10

Yekaterinburg

Conveners

6.11 IAEA Benchmark on EBR-II Shutdown Heat Removal Tests

• Vladimir Kriventsev (IAEA)
• Ethan Bates (TerraPower LLC.)

361. IAEA’s Coordinated Research Project on EBR-II Shutdown Heat Removal Tests: An Overview

Dr Vladimir Kriventsev (IAEA)

26/06/2017, 15:15

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

A Coordinated Research Project (CRP) on “Benchmark analysis of EBR-II Shutdown Heat Removal Tests (SHRT)” was launched by the International Atomic Energy Agency (IAEA) in 2012. A series of transient tests were conducted on the EBR-II reactor at Argonne National Laboratory (ANL) to improve the understanding of thermal hydraulics and neutronics of fast reactors. Shutdown heat removal tests...

4. EBR-II Passive Safety Demonstration Tests Benchmark Analyses

Ms Laural Briggs (Argonne National Laboratory)

26/06/2017, 15:25

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

In 2012, the International Atomic Energy Agency (IAEA) established a coordinated research project (CRP) on EBR-II Shutdown Heat Removal Tests (SHRT). The objectives of the CRP, which concluded in 2016, were to improve design and simulation capabilities in fast reactor neutronics, thermal hydraulics, plant dynamics, and safety analyses through benchmark analysis of two landmark tests from the...

70. IAEA NEUTRONICS BENCHMARK FOR EBR-II SHRT-45R

Ms Barbara Vezzoni (Karlsruhe Institute of Technology (Germany)), Mr Wilfred Van Rooijen (Research Institute of Nuclear Engineering (RINE), University of Fukui, (Japan))

26/06/2017, 15:45

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

A Coordinated Research Project (CRP) initiated by the International Atomic Energy Agency (IAEA) aimed to benchmark Shutdown Heat Removal Tests (SHRT) conducted at Experimental Breeder Reactor II (EBR-II). Two SHRT tests (SHRT-17 and SHRT-45R) representative, respectively of Protected Loss of Flow (PLOF) and Unprotected Loss of Flow (ULOF) transients were considered. The SHRT-45R benchmark...

372. Conclusions of a Benchmark Study on the EBR-II SHRT-45R Experiment

Ms Dalin Zhang (Xi'an Jiaotong University), Dr Ethan Bates (TerraPower)

26/06/2017, 16:05

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

This paper presents the conclusions of a 4 year benchmark study on the simulation of the EBR-II SHRT-45R experiment. The SHRT-45R experiment was an unprotected loss of flow transient where pump dynamics, natural convection, core and mechanical behavior played a large role in passively and safely limiting the power and temperature rise of the fuel assemblies. Participants from China, Germany,...

118. Thermal Hydraulic Investigation of EBR-II Instrumented Subassemblies during SHRT-17 and SHRT-45R Tests

Mr Partha Sarathy UPPALA (Indira Gandhi Centre for Atomic Research)

26/06/2017, 16:25

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

Experimental Breeder Reactor (EBR-II) was a U-Pu-Zr metal-alloy fuelled liquid-metal-cooled fast reactor, extensively used for conducting safety experiments. EBR-II was heavily instrumented to measure sodium flows and temperatures at various locations in the primary circuit including the temperature distribution inside the subassemblies (SA). Several transient tests were conducted on the...

84. Final Results and Lessons Learned from EBR-II SHRT-17 Benchmark Simulations

Mr Nikita Rtishchev (IBRAE RAN)

26/06/2017, 16:45

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

In 2012 the IAEA initiated a 4-year coordinated research project (CRP) “Benchmark Analyses of EBR-II Shutdown Heat Removal Tests”, with Argonne National Laboratory serving as the lead technical institution. Nineteen participants from eleven countries were involved in the project. The overall purpose of the CRP was to improve validation of state-of-the-art sodium-cooled fast reactor (SFR)...