A zero dimensional model for simulation of TRIGA Mark II dynamic response

Cammi, Antonio; Ponciroli, Roberto; Tigliole, A. Borio di; Magrotti, Giovanni; Prata, Michele; Chiesa, D.; Previtali, E.

doi:10.1016/j.pnucene.2013.04.002

Cited by 25 publications

(18 citation statements)

References 2 publications

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“…More recent studies [37]- [39] investigated the natural circulation in SMRs, such as CAREM-25 and REX-10 (Regional Energy Reactor-10 MWt), and TRIGA Mark II.…”

Section: Previous Studies On Dynamic Modelingmentioning

confidence: 99%

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Nonlinear dynamic modeling and simulation of a passively cooled small modular reactor

Arda

Holbert

2016

Progress in Nuclear Energy

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A nonlinear dynamic model for a passively cooled small modular reactor (SMR) is developed. The nuclear steam supply system (NSSS) model includes representations for reactor core, steam generator, pressurizer, hot leg riser and downcomer. The reactor core is modeled with the combination of: (1) neutronics, using point kinetics equations for reactor power and a single combined neutron group, and (2)

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“…More recent studies [37]- [39] investigated the natural circulation in SMRs, such as CAREM-25 and REX-10 (Regional Energy Reactor-10 MWt), and TRIGA Mark II.…”

Section: Previous Studies On Dynamic Modelingmentioning

confidence: 99%

“…The thermal resistance is constituted by a series of resistances due to the fuel, the gap between the fuel and cladding, the cladding, and the convective heat transfer between the outer surface of the cladding and coolant [39]. Thus, the global heat transfer resistance can be formulated as:…”

Section: Thermal Resistance Evaluationmentioning

confidence: 99%

Nonlinear dynamic modeling and simulation of a passively cooled small modular reactor

Arda

Holbert

2016

Progress in Nuclear Energy

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“…The thermal resistance is constituted by series of resistances due to the fuel, the gap between the fuel and cladding, the cladding, and the convective heat transfer between the outer surface of the cladding and coolant (Cammi et al, 2013). Thus, the global heat transfer resistance can be formulated as:…”

Section: Thermal Resistance Evaluationmentioning

confidence: 99%

“…This is a common practice that is used in other works also (Zvirin, 1982;Marcel et al, 2013b;Jang et al, 2011;Cammi et al, 2013).…”

Section: Pressure Lossesmentioning

confidence: 99%

A dynamic model of a passively cooled small modular reactor for controller design purposes

Arda

Holbert

2015

Nuclear Engineering and Design

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“…The TRIGA Mark II reactor of the University of Pavia was brought to its first criticality in 1965 and since then it has been used for several scientific and technical applications such as production of radioisotopes, nuclear activation analysis, development of boron neutron capture therapy in the medical field and reactor physics studies, thanks to the possibility of performing experimental measurements for the validation of reactor modelling codes. In this respect, a research activity was initiated since a few years, with the aim of implementing reliable simulation models for the analysis of reactor neutronics and thermal-hydraulics with an integrated approach (Cammi et al, 2013, Borio et al, 2014a, Chiesa et al, 2014a, Chiesa et al, 2014b.…”

Section: Introductionmentioning

confidence: 99%

Characterization of the TRIGA Mark II reactor full-power steady state

Cammi

Zanetti

Chiesa

et al. 2016

Nuclear Engineering and Design

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In this work, the characterization of the full-power steady state of the TRIGA Mark II nuclear reactor of the University of Pavia is performed by coupling Monte Carlo (MC) simulation for neutronics with "Multiphysics" model for thermalhydraulics. Neutronic analyses have been performed starting from a MC model of the entire reactor system, based on the MCNP5 code, that was already validated in fresh fuel and zero-power configuration (in which thermal effects are negligible) using the available experimental data as benchmark. In order to describe the full-power reactor configuration, the temperature distribution in the core is necessary. To evaluate it, a thermal-hydraulic model has been developed, using the power distribution results from MC simulation as input. The thermal-hydraulic model is focused on the core active region and takes into account sub-cooled boiling effects present at full reactor power. The obtained temperature distribution is then introduced in the MC model and a benchmark analysis is carried out to validate the model in fresh fuel and full-power configuration. The good agreement between experimental data and simulation results concerning full-power reactor criticality, proves the reliability of the adopted methodology of analysis, both from neutronics and thermal-hydraulics perspective.

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A zero dimensional model for simulation of TRIGA Mark II dynamic response

Cited by 25 publications

References 2 publications

Nonlinear dynamic modeling and simulation of a passively cooled small modular reactor

Nonlinear dynamic modeling and simulation of a passively cooled small modular reactor

A dynamic model of a passively cooled small modular reactor for controller design purposes

Characterization of the TRIGA Mark II reactor full-power steady state

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