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VGB POWERTECH 7 (2021) - International Journal for Generation and Storage of Electricity and Heat

VGB PowerTech - International Journal for Generation and Storage of Electricity and Heat. Issue 7 (2021). Technical Journal of the VGB PowerTech Association. Energy is us! Optimisation of power plants. Thermal waste utilisation.

VGB PowerTech - International Journal for Generation and Storage of Electricity and Heat. Issue 7 (2021).
Technical Journal of the VGB PowerTech Association. Energy is us!
Optimisation of power plants. Thermal waste utilisation.

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<strong>VGB</strong> PowerTech 7 l <strong>2021</strong><br />

Verification <strong>of</strong> SPACE code based on an MSGTR experiment at the ATLAS-PAFS facility<br />

C883<br />

F884 ~ 896<br />

C882<br />

97.1 kW based on the in<strong>for</strong>mation <strong>of</strong> the<br />

initial experiment condition. During the<br />

initial conditions, the major thermal hydraulic<br />

parameters, including the system<br />

pressure, fluid temperature, <strong>and</strong> mass<br />

flow rate, were reasonably consistent with<br />

the experiment condition. The calculation<br />

time started from -1000.0 s to 0.0 s <strong>and</strong><br />

all design parameters converged after<br />

-500.0 s. After checking the steady<br />

1 2 11 12 13<br />

NX = 1<br />

Fig. 4. Nodding diagram <strong>of</strong> PCCT using ‘3D’ option <strong>of</strong> SPACE code.<br />

NY = 13<br />

NZ = 14<br />

Tab. 1. Comparison results between initial condition <strong>of</strong> experiment <strong>and</strong> steady state results <strong>of</strong><br />

SPACE code.<br />

Parameter Experiment SPACE code Difference (%)<br />

Primary system<br />

Core power (MW) 1.627 1.627 0.00<br />

<strong>Heat</strong> loss (kW) 97.1 97.2 0.40<br />

Pressurizer (PZR) pressure (MPa) 15.52 15.50 0.13<br />

PZR level (m) 3.71 3.71 0.00<br />

Cold leg flow rate (kg/s) 1.9728 1.941 1.61<br />

Core inlet temp. (°C) 292.0 289.4 0.89<br />

Core outlet temp. (°C) 327.5 325.2 0.70<br />

Secondary system<br />

Steam flow rate (kg/s) 0.4019 0.4153 3.33<br />

Feed water flow rate (kg/s) 0.4209 0.4194 0.36<br />

Feed water temp. (°C) 233.3 233.3 0.00<br />

Steam dome pressure (MPa) 7.83 7.81 0.20<br />

Steam temp. (°C) 295.7 294.2 0.51<br />

SG collapsed water level (m) 4.97 4.97 0.00<br />

Passive Auxiliary Feedwater System (PAFS)<br />

Initial PCCT level (m) 3.8 3.8 0.00<br />

Initial PCCT temp. (°C) 28.8 28.8 0.00<br />

state condition, the transient calculation<br />

started at 0.0 s <strong>of</strong> the steady state condition.<br />

3.2 Transient analysis results<br />

According to the agreement <strong>of</strong> the ATLAS<br />

Domestic St<strong>and</strong>ard Problem-05, the experimental<br />

data should be confidential. There<strong>for</strong>e,<br />

all <strong>of</strong> the experiment results in this<br />

paper including the time frame (t*) were<br />

divided by an arbitrary value <strong>and</strong> plotted<br />

on the non-dimensional axis.<br />

3.2.1 Sequence <strong>of</strong> transient calculation<br />

result<br />

Ta b l e 2 summarizes the measured <strong>and</strong><br />

calculated sequences <strong>of</strong> a MSGTR-PAFS<br />

test. The transient was initiated with the<br />

MSGTR in normal condition. To initiate the<br />

MSGTR transient, the break valve was<br />

opened at 0.0 s with the pressurizer heater<br />

<strong>of</strong>f according to the experiment scenario.<br />

The break flow contributed to the steam<br />

generator overfill, <strong>and</strong> the collapsed water<br />

level <strong>of</strong> the SG-1 reached a set point <strong>of</strong><br />

HSGL signal, leading to the generation <strong>of</strong><br />

the HSGL signal. This signal was generated<br />

at a later time in the calculation case than<br />

it was in the experiment case. The reactor<br />

trip occurred simultaneously due to the<br />

HSGL signal, <strong>and</strong> the MSIVs <strong>and</strong> MFIVs<br />

were also closed after their respective delay<br />

times. After the MSIVs were closed, the<br />

pressure in steam generator was controlled<br />

by the cyclic operation <strong>of</strong> MSSVs. According<br />

to the experimental assumptions, the<br />

heater power which simulates the decay<br />

power had the ANS-73 decay curve applied<br />

<strong>for</strong> the experimental condition, <strong>and</strong> the<br />

heater power started after the reactor trip.<br />

For the calculation, time verse decay power<br />

data was applied in accordance with the<br />

experiment in<strong>for</strong>mation [4]. The time at<br />

which the MSSVs first opened in the experiment<br />

<strong>and</strong> the calculation results were<br />

the same after the HSGL signal was triggered.<br />

During this steam generator overfill<br />

period, the pressure in the primary system<br />

decreased substantially. As a result, when<br />

the primary system pressure decreased to<br />

the set point <strong>of</strong> the LPP trip, the LPP signal<br />

was triggered, <strong>and</strong> the SIP injection was<br />

initiated after the delay time. The collapsed<br />

water level <strong>of</strong> SG-2 decreased due to<br />

the decay power, then reached a set point<br />

<strong>of</strong> PAFS operation. Finally, the PAFS operation<br />

valve automatically opened <strong>and</strong> passive<br />

cooling using PAFS was initiated.<br />

3.2.2 Primary system behaviors<br />

The decay power was one <strong>of</strong> the important<br />

factors in this analysis, <strong>and</strong> the calculation<br />

results were consistent with the experimental<br />

result, as shown in F i g u r e 5 .<br />

F i g u r e 6 shows the measured <strong>and</strong> calculated<br />

break flow, which were normalized<br />

by the maximum value <strong>of</strong> the experiment.<br />

The break flow rate largely depended on<br />

the pressure difference between the primary<br />

<strong>and</strong> the secondary systems. There<strong>for</strong>e,<br />

as shown in F i g u r e 6 , the peak flow<br />

rate occurred at the beginning <strong>of</strong> transient.<br />

After the occurrence <strong>of</strong> peak flow, the<br />

break flow in the experiment case oscillated<br />

<strong>and</strong> gradually decreased. On the other<br />

h<strong>and</strong>, the calculation result shows that the<br />

break flow was maintained constantly. The<br />

break flow was deeply related to the difference<br />

between the pressures <strong>of</strong> the primary<br />

<strong>and</strong> secondary systems. After the pressure<br />

81

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