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Nuclear Production of Hydrogen, Fourth Information Exchange ...

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TRANSIENT MODELLING OF S-I CYCLE THERMOCHEMICAL HYDROGEN GENERATION COUPLED TO PEBBLE BED MODULAR REACTOR<br />

The extent <strong>of</strong> reaction in each reaction chamber is calculated via the above kinetics expressions.<br />

These expressions are dependent on the concentrations <strong>of</strong> the reactant and the temperature <strong>of</strong> the<br />

reaction chamber, via the Arrhenius expressions. This is expressed generally as:<br />

( , )<br />

X = X T<br />

(9)<br />

R C i<br />

Ideal gas law is assumed as the equation <strong>of</strong> state in the S-I/HyS cycle model. Comparison between<br />

ideal gas law and the Peng Robinson equation <strong>of</strong> state yielded a relative error <strong>of</strong> only 0.18% (Brown,<br />

2009). Thus, the assumption <strong>of</strong> ideal gas law in the model <strong>of</strong> the S-I/HyS cycle is justified.<br />

PV = M RT<br />

(10)<br />

R<br />

R<br />

The heat transfer through the intermediate heat exchanger is the crux <strong>of</strong> the coupled system. The<br />

heat transfer through the intermediate heat exchanger is given via the following simple expression:<br />

HX<br />

He<br />

R<br />

( h − h )<br />

Q = U ⋅ A ⋅ ΔT<br />

= m<br />

(11)<br />

He,in<br />

He,out<br />

PBMR-268 model<br />

The PBMR-268 is a pebble bed type high temperature gas-cooled reactor with a design power <strong>of</strong><br />

268 MWth. The PBMR-268 is helium-cooled and graphite-moderated, with a dynamic inner reflector<br />

composed <strong>of</strong> graphite balls. This reactor design has many important characteristics, namely passive<br />

safety. Additionally, the high coolant temperature makes it ideal for thermochemical hydrogen<br />

generation. A thermal model <strong>of</strong> a PBMR-268 was developed utilising the thermal-hydraulics code<br />

THERMIX-DIREKT. THERMIX-DIREKT solves the 2-D mass, energy and momentum balance equations<br />

for the Ergun’s resistance model for pebble bed reactors.<br />

A PBMR is a thermal reactor, thus delayed neutrons are the important factor in reactor response.<br />

A thermal reactor has a time constant <strong>of</strong> about 55 seconds. In the chemical plant, Section 2 and<br />

Section 3 have different response times. Section 2 has a response time on the order <strong>of</strong> 20 seconds,<br />

whereas Section 3 has a response time on the order <strong>of</strong> 500 seconds. The limiting reaction rate in the<br />

chemical plant is that <strong>of</strong> Section 3. Since the chemical plant is composed <strong>of</strong> cyclic processes, we know<br />

that the slowest reaction rate will occur in Section 3, the HI decomposition section. The response rate<br />

<strong>of</strong> Section 3 provides at least a first-order approximation <strong>of</strong> the overall plant response.<br />

The PBMR-268 model is derived from the PBMR-268 design. Numerous assumptions were made<br />

regarding the geometry <strong>of</strong> the PBMR-268 design in the benchmark specification. Some <strong>of</strong> the most<br />

important geometric simplifications are (Seker, 2005):<br />

• core is assumed to be 2-D (r,z);<br />

• flattening <strong>of</strong> the pebble bed’s upper surface;<br />

• flow channels within the reactor are parallel;<br />

• removal <strong>of</strong> the bottom cone;<br />

• removal <strong>of</strong> the de-fuel channel.<br />

The intra-pebble coolant flow is simplified such that the flow occurs at equal speed in parallel<br />

channels (Seker, 2005). The side reflector control rods are modelled as concentrations <strong>of</strong> boron in a<br />

concentric cylinder (Seker, 2005).<br />

A scaling analysis <strong>of</strong> the hydrogen generation by the thermochemical plant was performed. For a<br />

steady-state power <strong>of</strong> 268 MWth in the heat exchanger, the simplified model hydrogen production<br />

rate was scaled to 142.3 mol/s. In a transient scenario, this steady-state production rate will change.<br />

The nuclear reactor kinetics was modelled using simple point kinetics. The point kinetics model<br />

utilised in the calculation was developed as an analogue to the point kinetics module <strong>of</strong> the RELAP5<br />

code. The number <strong>of</strong> delayed neutron groups considered was six. A Doppler feedback coefficient <strong>of</strong><br />

-0.0095 was used. Xenon feedback was also modelled, although due to the time scales considered in<br />

this document the xenon feedback is not relevant and has almost no impact on the results.<br />

368 NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010

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