Nuclear Energy for New Europe 2009

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No: 703

Conference: Nuclear Energy for New Europe 2009

Title: A Dynamic Model of a Lead-Cooled Fast Reactor (LFR) with a Supercritical Water Steam Cycle

Theme: Emerging Reactor Designs

Author(s): Davide Papini, Antonio Cammi, Marco Colombo, Vito Memoli, Marco Ricotti

Contact : Davide Papini

E-mail: davide.papini@mail.polimi.it

Address: Politecnico di Milano - department of energy
20156 Milano

Country: Italy

The LFR (Lead Fast Reactor) is one of the six innovative concepts of nuclear reactors envisaged by the GIF (Generation IV International Forum) initiative for the long term evolution of the nuclear technology, in the direction of a more sustainable and economic power generation. Sixteen European organizations proposed to the European Commission the project of a European Lead-cooled SYstem (ELSY), a 600 MWe power reactor cooled with molten lead.
A linearized model, for the investigation of the dynamics of a lead cooled fast reactor with a supercritical water steam cycle, was developed. The reference design for the primary system is the ELSY reactor. In this paper a supercritical secondary circuit is studied. Such a configuration is competitive with the subcritical superheated steam configuration, in particular following the prevision of a lead working temperature increase. The supercritical water steam cycle is an attractive option for a nuclear power plant, hence it is of great interest to study its dynamic behaviour when it is coupled with the primary system of a nuclear reactor.
Suitable heat transfer correlations are required to duly model convective phenomena near the critical point region. A comparison of different correlations was carried out. The results show that Jackson correlation is a fair choice for the modelling of the process.
Two separate dynamic models, for primary and secondary loop, were developed, validated and coupled in order to describe the whole system.
Despite several limits brought by the linearization, the LFR system with a supercritical water steam cycle shows satisfactory results in the dynamic responses. Investigated perturbations concern reactor power, feedwater temperature and feedwater mass flow. The developed model provides a useful tool coping with the study of the system dynamics and can be considered a starting point for future investigations on the matter, e.g. when dealing with control design issues.

No:	703
Conference:	Nuclear Energy for New Europe 2009
Title:	A Dynamic Model of a Lead-Cooled Fast Reactor (LFR) with a Supercritical Water Steam Cycle
Theme:	Emerging Reactor Designs
Author(s):	Davide Papini, Antonio Cammi, Marco Colombo, Vito Memoli, Marco Ricotti
Contact :	Davide Papini
E-mail:	davide.papini@mail.polimi.it
Address:	Politecnico di Milano - department of energy 20156 Milano
Country:	Italy

The LFR (Lead Fast Reactor) is one of the six innovative concepts of nuclear reactors envisaged by the GIF (Generation IV International Forum) initiative for the long term evolution of the nuclear technology, in the direction of a more sustainable and economic power generation. Sixteen European organizations proposed to the European Commission the project of a European Lead-cooled SYstem (ELSY), a 600 MWe power reactor cooled with molten lead. A linearized model, for the investigation of the dynamics of a lead cooled fast reactor with a supercritical water steam cycle, was developed. The reference design for the primary system is the ELSY reactor. In this paper a supercritical secondary circuit is studied. Such a configuration is competitive with the subcritical superheated steam configuration, in particular following the prevision of a lead working temperature increase. The supercritical water steam cycle is an attractive option for a nuclear power plant, hence it is of great interest to study its dynamic behaviour when it is coupled with the primary system of a nuclear reactor. Suitable heat transfer correlations are required to duly model convective phenomena near the critical point region. A comparison of different correlations was carried out. The results show that Jackson correlation is a fair choice for the modelling of the process. Two separate dynamic models, for primary and secondary loop, were developed, validated and coupled in order to describe the whole system. Despite several limits brought by the linearization, the LFR system with a supercritical water steam cycle shows satisfactory results in the dynamic responses. Investigated perturbations concern reactor power, feedwater temperature and feedwater mass flow. The developed model provides a useful tool coping with the study of the system dynamics and can be considered a starting point for future investigations on the matter, e.g. when dealing with control design issues.