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atw 2018-02

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<strong>atw</strong> Vol. 63 (<strong>2018</strong>) | Issue 2 ı February<br />

ENERGY POLICY, ECONOMY AND LAW 82<br />

reactor core. It is used to support the reactor core and<br />

locate the reactor core components. On June 8, 2017, the<br />

installation of the ceramic components inside the second<br />

reactor core was finished, which means half of the<br />

installation progress of the main facilities in the nuclear<br />

island has been done. Before August 11, 2017, the fuel<br />

production line has produced 250,000 pebbles, which met<br />

the requirement of connecting to the grid for HTR-PM.<br />

The project is planned to be completed and put into operation<br />

at the end of 2017/beginning of <strong>2018</strong>, but probably<br />

it will be delayed (Figure 3). The design lifetime of<br />

HTR-PM is 40 years.<br />

| | Fig. 3.<br />

The construction of Shidao Bay HTGR conventional island was finished<br />

on June 27, 2015 (photo credits: Shidao Bay NPP).<br />

3 Safety features of HTGR<br />

One of the most important safety issues for nuclear power<br />

plant is decay heat removal. In the Three Mile Island and<br />

Fukushima Daiichi nuclear accidents, the reactor cores are<br />

overheated and melt down due to the failure of decay heat<br />

removal. In Chernobyl accident, the failure of decay heat<br />

removal system caused the resulting sequences after the<br />

initial exploration due to the fission power increment.<br />

So developing a highly reliable emergency core cooling<br />

system with reliable water and electricity supply is very<br />

important for a light water reactor (LWR).<br />

But for HTGR, inherent safety can be achieved based<br />

on three physical ideas: 1. using silicon carbide (SiC),<br />

which has very good heat-resistance, as the fuel cladding;<br />

2. lowering the volumetric power density of the reactor<br />

core significantly; 3. using identical small reactor modules<br />

to replace a large reactor in order to make sure that the<br />

reactor core won’t be heated to the temperature limit [7].<br />

Besides physical ideas, the safety of HTGR can be<br />

protected from three engineering designs:<br />

1. Multiple barriers to prevent the release of<br />

radioactivity<br />

The HTGR has three safety barriers to prevent the release<br />

of radioactivity. The first barrier is the fuel particles coated<br />

with SiC. The maximum temperature of the fuel particles<br />

is designed to be limited to 1,600 °C under any operation<br />

or accident conditions. Less than 1,600 °C, the coat of the<br />

particles can maintain integrated [8]. The second barrier<br />

is the pressure boundary of the primary circuit, which<br />

contains the reactor pressure vessel, the steam generator<br />

pressure vessel and the hot gas duct pressure vessel which<br />

connects the previous two vessels. The likelihood for<br />

these three vessels to have ruptures can be neglected. The<br />

third barrier is the bounding volume, which contains the<br />

primary circuit cabin, Helium purification cabin as well as<br />

fuel loading and unloading cabin. They can prevent the<br />

radioactive gas to be released into the atmosphere.<br />

2 Passive decay heat removal system<br />

The thermal design of HTGR has already considered that<br />

in case of any accidents, the cooling of the reactor core<br />

doesn’t need any active decay heat removal system. The<br />

decay heat in the reactor core can be removed from the<br />

core to the surface cooler outside of the reactor pressure<br />

vessel passively through heat conduction and radiation.<br />

Then the heat can be passed to the atmosphere from the<br />

surface cooler by nature convection. If the primary circuit<br />

lost pressure and the main and the auxiliary decay heat<br />

removal system are out of work, the decay heat can still be<br />

removed from the core to the outside. The reactor core<br />

meltdown can be avoided. Under accident conditions,<br />

because the decay heat cannot be removed by the main<br />

decay heat removal system, the temperature of the pebbles<br />

will be increased. In order to make sure the maximum<br />

temperature of the pebbles will not exceed 1,600 °C, some<br />

restrictions to the power density and geometry of the<br />

reactor core are necessary. That’s the reason why the<br />

capacity of the HTGR is usually small.<br />

3 Negative temperature coefficient has good reactivity<br />

compensation<br />

The reactor has a relatively high negative temperature<br />

coefficient for the fuel and moderator and if it is under<br />

normal condition, the margin between the maximum<br />

temperature of the pebbles and its limit is large. The<br />

negative temperature coefficient can give a good reactivity<br />

compensation. When a positive reactivity is introduced<br />

into the reactor, it can be automatically shut down thanks<br />

to the reactivity compensation from the negative temperature<br />

coefficient [9].<br />

The long term operation of HTR-10 and different<br />

safety experiments have proved the inherent safety of<br />

HTGR, which improved the public acceptance of nuclear<br />

reactors.<br />

4 Fuel technology<br />

In 2005, INET built a prototyping fuel-production facility<br />

with a capacity of 100,000 fuel elements per year. In order<br />

to solidify the fabrication level, INET started to construct<br />

HTGR fuel-production factory in Baotou, Northern China<br />

in 2013. The fuel-production equipment was installed in<br />

2014. In 2015, they started the commissioning and trial<br />

production. Some experiments have been done in Petten,<br />

the Netherlands. The irradiation test of five fuel spheres of<br />

the HTR-PM started in October 2012 in the high flux<br />

reactor (HFR) and finished on December 30, 2014. The<br />

fuel sphere quality, which is one of the key technologies in<br />

HTR-PM project, has been proved to meet the requirements<br />

[7].<br />

On August 15, 2016, the construction of the fuel<br />

production line in Baotou was finished and the fuel pebble<br />

production started. By July 17, 2017, the fuel production<br />

line has already produced 200,000 pebbles. It means<br />

that the fuel production of HTGR has shifted from trial<br />

production to industrial production. It also means that the<br />

fuel production technology of HTGR in China is leading<br />

the world, which has great significance for achieving<br />

commercialization and export of HTGR [10].<br />

When a fuel element is discharged from the bottom<br />

of the RPV to the fuel handling system, its burn-up is<br />

measured immediately. If its burn-up does not reach the<br />

design burn-up limit, it will be recharged into the reactor<br />

Energy Policy, Economy and Law<br />

Development of High Temperature Gas Cooled Reactor in China ı Wentao Guo and Michael Schorer

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