Full 3-D core calculations with refueling for the OPAL Research Reactor using Monte Carlo Code Serpent 2

Ferraro, Diego; Villarino, Eduardo

doi:10.1016/j.anucene.2016.02.004

Cited by 14 publications

(6 citation statements)

References 3 publications

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“…The resulting geometry is presented in Figure 3, where details for core modelling can be obtained in [4]. It can be observed that the mesh definition includes higher detail where it is required.…”

Section: Neutronic Modelmentioning

confidence: 99%

“…This model was validated, comparing the computational results with experimental measurements performed in a real-size physical model built by INVAP during early OPAL design engineering stages [3]. Furthermore, detailed 3D Serpent [2] Monte Carlo models are also available, which have been already validated with experimental data from reactor commissioning and operating cycles [4].…”

Section: Advanced Modelling In Neutronic and Thermohydraulicmentioning

confidence: 99%

“…Detailed OPAL neutronic models have been developed using Serpent 2 code, where several comparisons with experimental measurements have been carried out, showing very good agreement for neutron flux profiles, CR worth, and reactivity evolution with burnup for first cycles [4]. Novel capabilities available in Serpent v2.1.28 allows including advanced features such as: -Dynamic simulations including delayed neutrons simulation: Dynamic simulation mode [5] has recently included the delayed neutron modelling capability, which allows the simulation of complex subcritical scenarios [6].…”

Section: Neutronic Modelmentioning

confidence: 99%

“…With the aim of these capabilities, the available neutronic models developed in Serpent for OPAL [4] already validated with commissioning measurements were updated to consider: a) Dynamic behaviour calculations, including rod drop scenario. For such purpose, a series of sources were generated and further used including neutron and precursors distribution.…”

Section: Neutronic Modelmentioning

confidence: 99%

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A multi-physics analysis for the actuation of the SSS in opal reactor

Ferraro¹,

Alberto²,

Villarino³

et al. 2018

EPJ Nuclear Sci. Technol.

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Abstract. OPAL is a 20 MWth multi-purpose open-pool type Research Reactor located at Lucas Heights, Australia. It was designed, built and commissioned by INVAP between 2000 and 2006 and it has been operated by the Australia Nuclear Science and Technology Organization (ANSTO) showing a very good overall performance. On November 2016, OPAL reached 10 years of continuous operation, becoming one of the most reliable and available in its kind worldwide, with an unbeaten record of being fully operational 307 days a year. One of the enhanced safety features present in this state-of-art reactor is the availability of an independent, diverse and redundant Second Shutdown System (SSS), which consists in the drainage of the heavy water reflector contained in the Reflector Vessel. As far as high quality experimental data is available from reactor commissioning and operation stages and even from early component design validation stages, several models both regarding neutronic and thermo-hydraulic approaches have been developed during recent years using advanced calculations tools and the novel capabilities to couple them. These advanced models were developed in order to assess the capability of such codes to simulate and predict complex behaviours and develop highly detail analysis. In this framework, INVAP developed a three-dimensional CFD model that represents the detailed hydraulic behaviour of the Second Shutdown System for an actuation scenario, where the heavy water drainage 3D temporal profiles inside the Reflector Vessel can be obtained. This model was validated, comparing the computational results with experimental measurements performed in a real-size physical model built by INVAP during early OPAL design engineering stages. Furthermore, detailed 3D Serpent Monte Carlo models are also available, which have been already validated with experimental data from reactor commissioning and operating cycles. In the present work the neutronic and thermohydraulic models, available for OPAL reactor, are coupled by means of a shared unstructured mesh geometry definition of relevant zones inside the Reflector Vessel. Several scenarios, both regarding coupled and uncoupled neutronic & thermohydraulic behavior, are presented and analyzed, showing the capabilities to develop and manage advanced modelling that allows to predict multi-physics variables observed when an in-depth performance analysis of a Research Reactor like OPAL is carried out.

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Section: Neutronic Modelmentioning

confidence: 99%

Section: Advanced Modelling In Neutronic and Thermohydraulicmentioning

confidence: 99%

Section: Neutronic Modelmentioning

confidence: 99%

Section: Neutronic Modelmentioning

confidence: 99%

See 2 more Smart Citations

A multi-physics analysis for the actuation of the SSS in opal reactor

Ferraro¹,

Alberto²,

Villarino³

et al. 2018

EPJ Nuclear Sci. Technol.

Self Cite

View full text Add to dashboard Cite

show abstract

“…Por isso, os reatores de pesquisa construídos nas últimas décadas têm potência térmica mínima da ordem de 20 MW, chegando até aos 100 MW [14,15]. O crescimento do uso e da potência de reatores nucleares de pesquisa nas últimas décadas, por sua vez,…”

Section: Introductionunclassified

Desenvolvimento de um modelo para dimensionamento da capacidade produtiva de fábricas de combustível nuclear para reatores de pesquisa

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The AP‐Th 1000 – An advanced concept to use MOX of thorium in a closed fuel cycle

2020

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Summary This work presents the feasibility studies to convert the UO2 core of the Westinghouse AP1000 reactor to a U/Th core aiming at U/Th fuel recycling. The focus of the work is to establish a first core which allows normal operation of the AP1000 reactor and investigate a possible route for generating the 233U for U/Th fuel recycling. The converted core named AP‐Th1000 is divided in three homogenous zones with different UO2/ThO2 mass proportions. The reprocessing procedure envisioned is to separate fission products and Pu isotopes, retain Uranium, use this fuel material in subsequent fuel cycles and complement the required fissile material with U with enrichment below 20%. The goal was to gradually reduce the mass proportion of mined Uranium fuel and eventually attain a Th‐233U core with similar operation characteristics of current AP1000 core. We perform a detailed three‐dimensional full core analysis with the SERPENT code examining core reactivity, power density distribution, and also a preliminary closed cycle study for the first 4 cycles where the production of 233U are evaluated. The goal of converting the AP1000 reactor core to a U/ThO2 fuel cycle was partially accomplished. While the first cycle was thoroughly examined and met all requirements we were not able to find a route to migrate it to a prevalent Th cycle. Basically, two of the set of criteria adopted in the study proved to be too restrictive to attain this goal with homogenous assembly, namely U enrichment below 20% and not recycling Pu. The results indicate that removing these two criteria the conversion factor in the ensuing fuel cycles can be increased and possibly attain a Th cycle without compromising the economics of power generation. The design changes were the elimination of IFBA burnable absorbers and replacement of gray control bundles by black control bundles.

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Full 3-D core calculations with refueling for the OPAL Research Reactor using Monte Carlo Code Serpent 2

Cited by 14 publications

References 3 publications

A multi-physics analysis for the actuation of the SSS in opal reactor

A multi-physics analysis for the actuation of the SSS in opal reactor

Desenvolvimento de um modelo para dimensionamento da capacidade produtiva de fábricas de combustível nuclear para reatores de pesquisa

The AP‐Th 1000 – An advanced concept to use MOX of thorium in a closed fuel cycle

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