Benchmark specifications and data requirements for EBR-II shutdown heat removal tests SHRT-17 and SHRT-45R

Sumner, T.; Wei, Thomas Y. C.

doi:10.2172/1432465

Cited by 29 publications

(52 citation statements)

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“…In this paper, the benchmarked thermal‐hydraulic model is adopted to validate the modified Relap5 Mod3 code. A serious loss‐of‐flow test in the SHRT series, SHRT‐17, is one of these benchmark experiments and made available by the ANL . The transient test was started by the primary pumps trip with a full control rod insertion simultaneously.…”

Section: Benchmark and Application Of The Modified Relap5 Mod3 Codementioning

confidence: 99%

Modification and application of Relap5 Mod3 code to several types of nonwater-cooled advanced nuclear reactors

et al. 2017

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Section: Benchmark and Application Of The Modified Relap5 Mod3 Codementioning

confidence: 99%

Modification and application of Relap5 Mod3 code to several types of nonwater-cooled advanced nuclear reactors

et al. 2017

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“…Approach to EBR‐II neutronics modelling. From the left, first column: true geometry from the benchmark specifications ; second column: cylindrical geometry adopted for the Monte Carlo calculation and the generation of cross sections; third column: nodalisation of the whole core and localisation of materials for the criticality calculation; fourth column: modification of the cross sections to better represent the heterogeneity. Different colours represent unique, heterogeneous materials.…”

Section: Neutronic Modelmentioning

confidence: 99%

Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient

et al. 2016

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SUMMARYDuring the last decade the European activities in the field of nuclear fission research include the design of fast reactors cooled by liquid metals. Within this framework, the Fast REactor NEutronics/Thermal-hydraulICs (FRENETIC) code is being developed at Politecnico di Torino over the last few years. It implements a full-core coupled neutronic/thermalhydraulic model of a liquid-metal-cooled fast reactor as relevant for two of the six options currently under study within the framework of the Generation-IV International Forum, namely the lead-cooled fast reactors and the sodium-cooled fast reactors. The code validation process involves the participation in a coordinated research project of the International Atomic Energy Agency, aiming at testing different computational tools against the shutdown heat removal tests performed many years ago in the sodium-cooled Experimental Breeder Reactor-II (EBR-II) at Argonne National Laboratory, USA. In this paper, results of the FRENETIC analysis of one of the transients considered in the project, the unprotected EBR-II shutdown heat removal test SHRT-45R, are presented and compared to the measurements, providing the first validation of the coupled neutronic/thermal-hydraulic features of the FRENETIC code.

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“…The EBR-II benchmark is described in two documents, one of which details the thermal-hydraulic part (ANL-ARC-226 [3]), while the other document describes the neutronic benchmark (ANL-ARC-228 [4]). The neutronic benchmark consists basically of a detailed description of the EBR-II core at the time of the SHRT-45R experiment.…”

Section: Neutronic Benchmarkmentioning

confidence: 99%

“…The primary system also features an Electromagnetic Pump (EMP, also known as auxiliary pump), for which no models are available in RELAP. In the actual measurement, natural circulation was augmented by the action of the auxiliary pump (more details can be found in [4]). Since it is difficult to (arbitrarily) replace the EM pump with an equivalent, conventional pump, it was decided not to implement the EM pump as such.…”

Section: The Relap Modelmentioning

confidence: 99%

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Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment with ERANOS and RELAP

Rooijen

Mochizuki

2015

Science and Technology of Nuclear Installations

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This paper presents the results of the analysis of the Unprotected Loss of Flow (ULOF) experiment SHRT-45R performed in the EBR-II fast reactor. These experiments are being analyzed in the scope of a benchmark exercise coordinated by the IAEA. The SHRT-45R benchmark contains a neutronic and a thermal-hydraulic part and results are presented for both. Neutronic calculations are performed with the ERANOS2.0 code in combination with various sets of nuclear data. The thermal-hydraulic evaluation is done with RELAP5-3D. The results are that the major neutronic parameters are well predicted with error margins on the order of 1%. The thermal-hydraulic results are less favourable: a consistent overestimation of the outlet temperature occurs in combination with erroneous flow distribution. Observed differences with measured data cannot be explained easily. The work presented in this paper was undertaken to investigate and validate the effectiveness of the calculational tools and data that are commonly used in our lab for the design and analysis of liquid metal cooled fast reactors.

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Benchmark specifications and data requirements for EBR-II shutdown heat removal tests SHRT-17 and SHRT-45R

Cited by 29 publications

References 0 publications

Modification and application of Relap5 Mod3 code to several types of nonwater-cooled advanced nuclear reactors

Modification and application of Relap5 Mod3 code to several types of nonwater-cooled advanced nuclear reactors

Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient

Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment with ERANOS and RELAP

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