Thermodynamic modeling of high-temperature

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Numerical Heat Transfer 2015 ... high temperature nuclear reactor HTGR/VHTR combined cycle with ... two steam turbines for electric energy generation and two heat exchangers for hydrogen production at ... low pressure (LP) steams. .... working fluid and the helium directly flows through the reactor, graphical moderator ...
Eurotherm Seminar No 109 Numerical Heat Transfer 2015 27-30 September 2015, Gliwice-Warsaw, Poland Eds.: A.J. Nowak, J. Banaszek, B. Šarler

Thermodynamic modeling of high-temperature combined cycle for hydrogen and electricity co-production – numerical analysis Michał Dudek*, Marek Jaszczur, Zygmunt Kolenda, Inga Polepszyc Department of Fundamental Research in Energy Engineering AGH University of Science and Technology, al. Mickiewicza 30, 30-059 Kraków, Poland e-mail: [email protected]

Key words: high temperature nuclear reactor, HTGR, hydrogen production, combined cycle. Abstract The high (HTGR) and Very High (VHTR) Temperature Nuclear Reactors are the most innovative designs and belong to the most advanced fourth generation gas-cooled reactor technology. Those types of reactors are designed to have an outlet temperature about 800oC and 1000°C for HTGR and VHTR respectively. Such systems are able to generate electric energy and supply process heat to a broad spectrum of hightemperature and energy-intensive non-electric and thermal processes. In this paper numerical analysis of high temperature nuclear reactor HTGR/VHTR combined cycle with co-production of hydrogen and electricity has been done. The presented cycle consists of a three subsidiary circuits with gas turbine and two steam turbines for electric energy generation and two heat exchangers for hydrogen production at high or medium temperature. The results show that such a combination allows significant increase of energy efficiency to about 60% (at the reactor outlet temperature 1273K) and decrease cost of hydrogen production.

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Introduction

The growing demand for electricity and contemporary development of nuclear power technology, computer technology and materials science allow today design and implement new solutions for nuclear energy, energy security as well as an energy conversion system, to lower unit cost of energy conversion and new possibilities in energy and fuel production. New generation of nuclear reactors are most innovative constructions and belongs to the most advanced reactor technology. HTGR/VHTR are gascooled reactors which gives possibilities to use high outlet temperature from 800oC to 1000°C for HTGR and VHTR respectively [2,6]. Nowadays, new generation of power plants working in combined cycle represents the most advanced power generation system and allow to achieve thermal efficiencies up to 60 percent, contrary to about of 33% of conventional power generation which utilize fossil fuels [2,5,6]. Much of the wasted energy in gas turbine cycles appears in hot exhaust gases from the combustion process. To increase the overall efficiency of thermal power plants, different processes can be combined to recover and utilize the residual heat energy in hot exhaust gases. Such cycle operation employs a heat recovery steam generator (HRSG) that uses heat from high temperature gas turbine exhaust gases to produce steam, which is then supplied to a steam turbine to generate additional electric power [5,9,10]. The most common type of combined cycle power plant utilizing exhausted gases is called a gas turbine combined cycle (GTCC) power plant. Because gases turbines have low efficiency in the simple operation cycle, the output produced by the steam turbine accounts for about half of the GTCC plant output [18,19]. The current projects and configurations for GTCC depend on the exhausted gases characteristics and its temperature. The exhaust gases from a gas turbine can actually reach 600ºC [9,10,14]. The power plant working in GTCC may produce steam at different pressure to optimize energy recovery system, usually it contains three sections of heat exchanger modules – for high pressure (HP), intermediate pressure (IP), low pressure (LP) steams. The main constraints in operations of the GTCC power plant HRSG systems are, is that located directly after gas turbines where changes in temperature and pressure of the exhaust gases may cause significant thermal and mechanical stresses [9,10,19]. Additionally, when such plant will be used in a load-following operation mode, which is typical and can lead to a large thermal stress in practical application and can eventual damage some components of the system. Operating conditions for the steam turbine are directly coupled with the gas turbine and heat recovery system [15,18,19]. The above show that complex system requires specific conditions to work properly. The situation has become even more complex if additional heat exchanger is installed before or after gas turbine in order to extract

Michał Dudek, Marek Jaszczur, Zygmunt Kolenda, Inga Polepszyc heat for high temperature thermochemical processes. Finding proper conditions for all elements which allows efficient work of the cycle become a very complex problem [5,9,10]. Coupling the high temperature nuclear reactor with combined cycle for electricity production and with co-production of hydrogen is a very promising new way in energy generation[18,19]. The first historical constructions of high-temperature nuclear reactors are shown in Table 1. Table 1: Presents historical solutions of high temperature nuclear reactor.

Localization Power [MWt/MWe] Construction Helium Temperature [Inlet/Outlet]°C Helium Pressure [Bar] Power Density [MW/m3] Fuel forms Degree of enrichment Exploitation Period

Dragon

Peach Bottom

AVR

Fort St. Vrain

THTR

HTTR

HTR-10

UK 20

US 115/40

Germany 46/15

US 842/330

Germany 750/300

Japan 30

China 10

Cylindrical 350/750

Cylindrical 377/750

Spherical 270/950

Hexagonal 400/775

Spherical 270/750

Hexagonal 395/950

Spherical 300/900

20

22,5

11

48

40

40

20

14

8,3

2,3

6,3

6

2,5

2

TRISO LEU/HEU 20% U235 1967–1974

BISO HEU >20% U235 1968–1988

TRISO HEU >20% U235 1979–1989

BISO HEU >20% U235 1985–1989

TRISO LEU