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Innovation in Global Power - Parsons Brinckerhoff

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Thermal – Achiev<strong>in</strong>g New Efficiencies, Reduc<strong>in</strong>g Carbon Emissions<br />

http://www.pbworld.com/news_events/publications/network/<br />

The basic concept would allow a large nuclear power plant<br />

with a typical output of 800 to 1700 MWe to be comb<strong>in</strong>ed<br />

with a 300 MW CCGT generat<strong>in</strong>g unit. L<strong>in</strong>k<strong>in</strong>g the steamcycles<br />

of the two plants enables them to operate as an<br />

<strong>in</strong>tegrated power production unit and reduces losses of<br />

potential output, <strong>in</strong>creas<strong>in</strong>g total efficiency. Cycle efficiency<br />

ga<strong>in</strong>s enable the CCGT to contribute an <strong>in</strong>creased output for<br />

no additional fuel, with the efficiency of convert<strong>in</strong>g the energy<br />

<strong>in</strong> the gas to electricity <strong>in</strong>creased to about 62 percent.<br />

How NuGas TM Works<br />

Although a CCGT system has a high thermal efficiency, it<br />

relies on us<strong>in</strong>g the heat from the exhaust gases of the gas<br />

turb<strong>in</strong>e to boil water to produce steam that drives the<br />

turb<strong>in</strong>e. As the exhaust gases cool, water is evaporated <strong>in</strong><br />

the boiler tubes but temperature differences of up to 400ºF<br />

(200ºC) arise <strong>in</strong> the boiler due to the large amount of heat<br />

needed to evaporate the water. These temperature differences<br />

limit the potential work that can be extracted from the<br />

steam, reduc<strong>in</strong>g the output of the steam cycle.<br />

The NuGas TM cycle overcomes this limitation by ‘borrow<strong>in</strong>g’ a<br />

small proportion (typically 10 percent) of the steam from the<br />

nuclear steam cycle (po<strong>in</strong>t ‘A’ on Figure 1). The dry saturated<br />

steam is superheated us<strong>in</strong>g the exhaust heat of the gas<br />

turb<strong>in</strong>e. The high temperature steam (‘B’) is then used to<br />

drive a separate conventional condens<strong>in</strong>g steam turb<strong>in</strong>e to<br />

provide additional output from the plant. Superheat<strong>in</strong>g steam<br />

rather than boil<strong>in</strong>g water enables a much lower temperature<br />

difference to be ma<strong>in</strong>ta<strong>in</strong>ed <strong>in</strong> the heat recovery system,<br />

maximiz<strong>in</strong>g the value of the energy recovered.<br />

The heat <strong>in</strong> the gas turb<strong>in</strong>e exhaust flow between about<br />

570ºF and 320ºF (300ºC and 160ºC) is recovered via a high<br />

temperature economizer (‘C’) to generate high temperature<br />

Figure 1: Schematic Comb<strong>in</strong>ation of the Steam Cycles.<br />

feedwater, which is returned to the nuclear cycle (‘D’),<br />

ensur<strong>in</strong>g that the <strong>in</strong>let temperature to the steam generator<br />

is ma<strong>in</strong>ta<strong>in</strong>ed close to the design value.<br />

The heat <strong>in</strong> the gas turb<strong>in</strong>e exhaust below about 320ºF (160ºC)<br />

(‘E’) is used to heat part of the condensate from the high<br />

temperature steam turb<strong>in</strong>e (‘F’) before it is deaerated and<br />

returned to the nuclear cycle feed pumps (‘G’). The rema<strong>in</strong><strong>in</strong>g<br />

condensate from the high temperature steam turb<strong>in</strong>e is<br />

returned to the nuclear cycle condensate system (‘H’).<br />

The flows of energy around the cycle differ somewhat to<br />

those <strong>in</strong> a conventional CCGT. Figure 2 shows a simplified<br />

Sankey diagram for the NuGas TM cycle, <strong>in</strong>clud<strong>in</strong>g the energy<br />

exchanges between the CCGT and PWR cycles shown along<br />

the lower edge of the diagram.<br />

Identify<strong>in</strong>g the separate performance of the CCGT cycle<br />

when it is l<strong>in</strong>ked to the PWR cycle requires that the design<br />

PWR energy balance be ma<strong>in</strong>ta<strong>in</strong>ed. Thus, the CCGT returns<br />

power to the PWR to compensate for the reduction <strong>in</strong><br />

output due to the ‘borrowed’ steam and returns rejected<br />

heat <strong>in</strong> the CCGT cool<strong>in</strong>g water to the PWR to account<br />

for the reduced heat rejection from the nuclear turb<strong>in</strong>e<br />

condenser. The diagram therefore shows the additional<br />

energy <strong>in</strong>put, the additional losses and the additional power<br />

generated by the cycle, demonstrat<strong>in</strong>g its high efficiency.<br />

Safety Considerations<br />

Downstream failure is limited. The extraction of steam<br />

from the ma<strong>in</strong> steam system has the potential to disturb<br />

reactor operat<strong>in</strong>g conditions. However, the PWR system is<br />

designed to allow for a 10 percent step change <strong>in</strong> flow to the<br />

ma<strong>in</strong> steam turb<strong>in</strong>e without exceed<strong>in</strong>g the appropriate limits<br />

for a frequent operat<strong>in</strong>g condition. It is likely, nevertheless,<br />

Figure 2: Simplified Sankey Diagram for NuGas Cycle.<br />

<br />

9 PB Network #68 / August 2008

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