Research Papers: Nuclear Power

Simulation Model of a Passive Decay Heat Removal System for Lead-Cooled Fast Reactors

[+] Author and Article Information
Lorenzo Damiani

University of Genoa,
Via Montallegro 1,
Genoa 16145, Italy
e-mail: Lorenzo.Damiani@unige.it

Alessandro Pini Prato

University of Genoa,
Via Montallegro 1,
Genoa 16145, Italy
e-mail: salabi@unige.it

Contributed by the Nuclear Division of ASME for publication in the JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER. Manuscript received February 1, 2013; final manuscript received August 6, 2014; published online October 7, 2014. Editor: David Wisler.

J. Eng. Gas Turbines Power 137(3), 032901 (Oct 07, 2014) (8 pages) Paper No: GTP-13-1033; doi: 10.1115/1.4028459 History: Received February 01, 2013; Revised August 06, 2014

The generation IV lead cooled fast reactors are of particular interest for the Italian research: several influential companies (Ansaldo Nucleare, ENEA) are involved in these important European R&D projects. At present, one significant European project in progress is lead cooled European advanced demonstrator reactor (LEADER) which includes, among its goals, the construction of a lead-cooled fast reactor demonstrator, advanced lead fast reactor European demonstrator (ALFRED). The demonstrator has to include technical solutions that simplify the construction phase and assure full safety in operation; according to the latest guidelines, ALFRED final configuration will be characterized by a secondary loop providing bayonet-tube steam generators. The authors have addressed the issue of bayonet-tube steam generators proposing the external boiling bayonet steam generator (EBBSG) system, in which the reaction heat is extracted from the lead by means of coolant under vapor phase. This is possible thanks to an external feed-water boiling, based on the known Loeffler scheme, coupled to the bayonet tube concept. In the present paper, the authors propose a decay heat removal (DHR) system to match the EBBSG scheme. The DHR system is fully passive, exploiting natural circulation phenomena. The performance of the proposed DHR system is investigated through a Matlab-Simulink model. The results are satisfactory since, according to the simulations, the proposed DHR system is able to keep the primary coolant temperature within a safety range for a sufficient time, avoiding the lead freezing or over-heating.

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Fig. 3

Scheme of the SNC–DHR startup loop

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Fig. 2

Arrangement of reactor main components and side view of one heat exchanger

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Fig. 1

Scheme of the EBBSG system

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Fig. 4

Scheme of the SNC–DHR operative loop

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Fig. 6

Scheme of the lead loop

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Fig. 8

Thermal flows of decay, bayonets heat exchanger and condenser

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Fig. 10

Mass flow rates in the bayonets loop and in the condenser loop

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Fig. 11

Temperatures of the saturated steam and of the condensate

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Fig. 7

Lead temperatures in the reactor for lead forced circulation



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