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atw 2018-04v6

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<strong>atw</strong> Vol. 63 (<strong>2018</strong>) | Issue 4 ı April<br />

OPERATION AND NEW BUILD 234<br />

increases compared to the existing<br />

IHX loop.<br />

The following is the major comparison<br />

of the result of reference<br />

model and bypass mode model.<br />

Mass flow IHX loop Bypass Mode Loop<br />

Heat Exchanger 1 49839 50000<br />

Steam Generator 2 208359 214580<br />

Heat Exchanger 3 902043 918581<br />

| | Tab. 3.<br />

IHX Loop and Bypass Mode IHX Loop: Mass Flow Comparison.<br />

Pumping power<br />

When IHX loop and bypass modeadded<br />

IHX loop were compared, mass<br />

flow of m 10 and m 14 in the bypass<br />

mode-added loop was greater compared<br />

to the mass flow of m 5 and m 8 in<br />

the existing loop, as shown in Table 3.<br />

IHX loop<br />

(MWt)<br />

| | Tab. 4.<br />

IHX Loop and Bypass Mode IHX loop: Pumping Power Comparison.<br />

As shown in Table 4, depending on<br />

the difference of mass flow value,<br />

pumping power used in the pump also<br />

can be high in steam generator 2 and<br />

heat exchanger 3. However, although<br />

pumping power is higher in the bypass<br />

IHX loop, by reheating, efficiency of<br />

steam generator 2 increased from<br />

53.79 % to 54.4 %, and that of heat<br />

exchanger 3 increased from 45.83 %<br />

to 45.87 %; accordingly, it is seen that<br />

the value of Power increased. As a<br />

result, Net Power that considered<br />

pumping power in Total Power was<br />

178.6 MWt in the present IHX<br />

loop, but the IHX loop to which<br />

bypass mode was added increased<br />

to 185.3 MWt, as shown in Table 5.<br />

| | Tab. 5.<br />

IHX loop and Bypass mode IHX loop: Power Comparison.<br />

Bypass mode loop<br />

(MWt)<br />

Steam Generator 2 1.091 1.123<br />

Heat Exchanger 3 9.82 10<br />

Power<br />

IHX loop<br />

(MWt)<br />

Bypass mode loop<br />

(MWt)<br />

Heat Exchanger 1 37.37 37.37<br />

Steam Generator 2 94.63 99.7<br />

Heat Exchanger 3 57.46 59.34<br />

Net Power 178.6 185.3<br />

Since the assumption was that<br />

constant heat was supplied from the<br />

primary system, it is seen that the<br />

efficiency of the bypass model where<br />

net power is high, and it is judged that<br />

efficiency optimization model can be<br />

formulated by detailed design.<br />

4 Conclusion<br />

In this study, VHTR system was<br />

modelled for supplying high temperature<br />

heat, by distribution, produced in<br />

the high temperature gas furnace to<br />

hydrogen producing equipment and<br />

power generation equipment.<br />

Provided that high temperature<br />

gas- cooled reactor is located in<br />

primary system, the secondary system<br />

where hydrogen production and<br />

power supply are possible were<br />

explained. The helium that flows in<br />

the nuclear reactor first passes<br />

through the HX (heat exchanger)<br />

whose purpose is the production of<br />

hydrogen, and secondly and thirdly<br />

pass through the steam generator<br />

composed of super critical carbon<br />

dioxide cycle, and heat exchanger,<br />

respectively, producing the process<br />

heat and power. In order to analyze<br />

existing IHX loop model and bypass<br />

mode-added IHX loop model, the<br />

present authors studied the input &<br />

output conditions and output change<br />

of each steam generator and heat<br />

exchanger, and based on this result,<br />

by designing IHX loop in the power<br />

production part in detail, the authors<br />

performed the calculation of thermodynamic<br />

physical value and efficiency<br />

at each point. Additionally, the<br />

authors studied the change regarding<br />

electricity output and efficiency<br />

according to bypass mode, when<br />

reheating cycle is added, the possibility<br />

on the efficiency optimization<br />

was proposed.<br />

References<br />

[1] Kim. Y. W., 2015, Nuclear Hydrogen<br />

Production Technology development<br />

Using Very High Temperature Reactor,<br />

Trans. Korean Soc. Mech. Eng. C, Vol. 3,<br />

No. 4, pp. 299~305.<br />

[2] Chang. J. H., 2006, Current Status of<br />

Nuclear Hydrogen Development,<br />

Journal of Energy Engineering, Vol.15,<br />

No.2, pp. 127~137.<br />

[3] Lee. S. I., 2015, Heat Balance Study<br />

on Integrated Cycles for Hydrogen<br />

and Electricity Generation in VHTR,<br />

Transaction of the KNS Spring Meeting.<br />

[4] Sung. H. C., 2012, Development of<br />

Ultra-Supercritical (USC) Power Plant,<br />

Trans. Korean Soc. Mech. Eng. B,<br />

Vol. 36, No.2, pp.205~210.<br />

[5] Yeom Chung-seop, Im Dong-ryeol,<br />

Lee Jung-ik, 2014, Trend of Electricity<br />

Generation Technology using supercritical<br />

CO 2 , Institute for Advanced<br />

Engineering, KIC News, Volume 17,<br />

No.1.<br />

[6] K.C.Cotton,1998, Evaluating and<br />

Improving Steam Turbine Performance,<br />

2 nd edition, Cotton Fact Inc.<br />

[7] F-Chart Software, 2016,<br />

Engineering Equation Solver,<br />

http://www.fchart.com/ees/<br />

[8] NGNP Conceptual Design Report/Steam<br />

Cycle Modular Helium Reactor<br />

(SC-MHR) Demonstration Plant,<br />

Table 3-6 SC-MHR Conceptual Design<br />

Point Design Parameter.<br />

[9] SangIL Lee, Yeon Jae Yoo, Gyunyoung<br />

Heo, Soyoung Park, Yeon Kwan Kang,<br />

Heat Balance Study on Integrated<br />

Cycles for Hydrogen and Electricity<br />

Generation in VHTR-Part 2, Korean<br />

Nuclear Society Autumn Meeting,<br />

Oct 28-30, 2015.<br />

Authors<br />

SangIL Lee<br />

YeonJae Yoo<br />

Deok Hoon Kye<br />

Department of Nuclear Team<br />

Power & Energy Plant Division<br />

Hyundai Engineering Company<br />

Seoul, Korea<br />

Gyunyoung Heo<br />

Eojin Jeon<br />

Soyoung Park<br />

Department of Nuclear<br />

Engineering<br />

Kyung Hee University<br />

Yongin Korea<br />

Operation and New Build<br />

Heat Balance Analysis for Energy Conversion Systems of VHTR ı SangIL Lee, YeonJae Yoo, Deok Hoon Kye, Gyunyoung Heo, Eojin Jeon and Soyoung Park

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