Research Article  Open Access
Preliminary Development of Thermal Power Calculation Code HPower for a Supercritical Water Reactor
Abstract
SCWR (Supercritical Water Reactor) is one of the promising Generation IV nuclear systems, which has higher thermal power efficiency than current pressurized water reactor. It is necessary to perform the thermal equilibrium and thermal power calculation for the conceptual design and further monitoring and calibration of the SCWR. One visual software named HPower was developed to calculate thermal power and its uncertainty of SCWR, in which the advanced IAPWSIF97 industrial formulation was used to calculate the thermodynamic properties of water and steam. The ISO51674: 2003 standard was incorporated in the code as the basis of orifice plate to compute the flow rate. New heat balance model and uncertainty estimate have also been included in the code. In order to validate HPower, an assessment was carried out by using data published by US and Qinshan Phase II. The results showed that HPower was able to estimate the thermal power of SCWR.
1. Introduction
SCWR (Supercritical Water Reactor) is one of the promising Generation IV nuclear systems, which has higher thermal power efficiency than current pressurized water reactor. Compared to the currently running water coolant reactors, SCWR has the higher thermal efficiency and safety, which makes it a more promising advanced nuclear energy system. The concept of SCWR was originally put forward by Westinghouse and GE (General Electric) in the 1950s and preliminarily studied by the United States and the former Soviet Union from 1950s to 1960s. In the 1990s, Dobashi et al. [1] proposed the concept of SCWR again and made a further development in this area.
For reactor operating more safely, stably, and economically, the accurate calibration for real thermal power has important significance in reactor design and analysis. It is necessary to develop a special thermal power calculation code for SCWR, while there is no available program published in the world. This paper preliminarily developed visual software named HPower to calculate SCWR thermal power and its uncertainty based on heat balance method, which has been applied to current PWRs [2].
According to the various conceptual SCWR designs [3–5], HPower divided SCWR into two groups: one is the singleloop type and the other is the doubleloop type. The validation of HPower consists of two parts: for the singleloop SCWR, the data published by Jacopo [6] was used, while for the doubleloop SCWR, the values of Qinshan Phase II [7] were used; though it is not the SCWR, we just use it for preliminary validation since the exact detail design data was rarely published.
IAPWS is an international nonprofit association concerned with the properties of water and steam, particularly thermodynamic properties. In 1997, IAPWS adopted the “IAPWS Industrial Formulation 1997 for the Thermodynamic Properties of Water and Steam” for industrial use [8], called IAPWSIF97 for short, which replaced the previous industrial formulation IFC67 [9] published in 1967.
We have done lots of researches and work in comparing IAPWSIF97 with IFC67 in several aspects. The result showed that IAPWSIF97 improves significantly in boundary consistency and accuracy and calculation speed [10], which makes it more extensive use in power industry nowadays.
HPower adopted IAPWSIF97 to calculate thermodynamic properties (including specific volume, specific enthalpy, and viscosity) of water. The code covers all range of IAPWSIF97 , , , ), which has been divided into five regions.
2. Theoretical Modeling
The modules of HPower are given in Figure 1, where READDT is the reading data subroutine, NUSOLV is numerical calculation subroutine, THPROP is the subroutine which calculates the thermodynamic properties of water and steam, FLOWRT is the subroutine for flow rate calculation, ERCALC subroutine is for the uncertainty estimation, and OUTPUT is the output data subroutine.
HPower provides a visual interface for users and has high module independence, which makes it a practical code in SCWR analysis.
2.1. Thermodynamic Properties Subroutine
2.1.1. Subroutine Flow Chart
The range of IAPWSIF97 is divided into five subareas; each of them has a basic equation. To make the program more concise and readable, this subroutine used the compiling method of modularization; that is, separate districts of thermodynamics equation were written into separate subroutine.
We can directly obtain the thermophysical properties from pressure and temperature values using the basic equations except region 3. Subregion 3 does not have the formula which can calculate other various thermal parameters directly through the temperature and pressure; it can only rely on iteration calculation. In this subroutine, the first pressure calculation uses temperature and a small specific volume which was chosen as initial value. If the difference between the calculated value of pressure and user input values is positive, the value of specific volume increases incremental quantity ratio by half and continues the iteration until the pressure difference is less than condition of convergence. The iteration is over and other properties can be calculated.
Through this kind of iteration and close proximity to the input value by increasing incremental quantity in halving bisection method, not only the disadvantages of the increased specific volume increment are too small to calculate quickly was avoided, but also the accuracy of calculation can be ensured.
The subroutine of water and steam thermodynamic properties has been totally developed according to the flow chart shown in Figure 2.
2.1.2. Subroutine Calculation Verification
In order to do the verification, we list the calculation results together with those given by IAPWSIF97 in Table 1. We can see that the present results are in good agreement with those given by IAPWSIF97, so that the thermodynamic properties calculated by HPower are valid.

2.2. Flow Rate Calculation Subroutine
The main feedwater flow rate of the steam generator can be measured by orifice plate, which is widely used in measurement of fluid flow. This part is based on the ISO 5167 standard in [11].
As the schematic diagram shown in Figure 3, upstream fluid pressure is obtained by (1) taking pressure loss caused by the existence of orifice plate into account:
HPower adopted the following equation for flow rate measurement: where is mass flow rate, is ratio of (diameter of orifice at operating conditions) and (diameter of internal pipe at operating conditions), is expansibility factor (for compressible fluid, ), is differential pressure, is the density of upstream, and is discharge coefficient determined by ReaderHarris/Gallagher equation as follows: If mm, (4) should add the following term:
As we can see from the above equation, discharge coefficient depends on the Reynolds number , which is dependent on in turn, so the calculation of mass flow rate has to be iterated.
Diameters in the formula for calculating should be corrected due to the difference of temperature between working condition and measurement. If there is drain hole (diameter is ) on the plate, the should be corrected by the following equation: where the have already been corrected by temperature as follows: where is the measurement value under the standard temperature is the coefficient of linear expansion, and is the operating temperature.
is the Reynolds number calculated by (diameter of internal pipe at operating conditions), dimensionless parameters presenting the ratio of the inertia force and viscous force of upstream, calculated by the following equation: where is viscosity of the fluid at the working conditions, which is obtained by the thermodynamic properties subroutine.
is the ratio of the distance from the upstream tapping to the upstream face of the orifice plate and the pipe diameter, and the value selection of its conditions is as follows:
is the ratio of the distance from the downstream tapping to the downstream face of the orifice plate and the pipe diameter, and the value selection of its conditions is as follows:
The uncertainty of the feedwater flow measured and calculated by orifice plate and relevant equations will be given in Section 3.2. The computer verification of this subroutine will be integrated in Section 4.2.
2.3. SingleLoop SCWR Program
In singleloop type SCWR, the coolant is supercritical water which will be operated above the critical point of water . The coolant remains singlephase when operated above the critical point, which is a stupendous advantage for it will eliminate coolant boiling throughout the system. The no need for recirculation results in the elimination of pressurizer, jet pumps, steam generators, and steam separators. This direct cycle type is greatly simplified as shown in Figure 4.
The thermal power in this type can be calculated with thermal balance using measured values, including inlet and outlet temperatures, working pressure, flow rate of coolant, and the practical speed of pump. The thermal power was obtained by the following equation: where (kg/s) is the flow rate of the coolant in the loop, (tr/min) is the practical speed of pump, (tr/min) is the ideal speed of pump, and (kj/kg) is the difference between the enthalpy at the hot leg and the cold leg. The enthalpies are calculated using THPROP subroutine.
2.4. DoubleLoop SCWR Program
Some conceptual designs of doubleloop SCWR have been put forward, like CANDUSCWR with a steam generator proposed by Dr. William Fatoux [12] and a pressurized water reactor cooled with supercritical water in the primary loop proposed by Vogt et al. [13]. Doubleloop SCWR drives a turbine by the steams from the steam generator in the second loop indirectly as shown in Figure 5.
Heat balance method in this type of SCWR is based on the steam generator approximation enthalpy balance. HPower calculate the thermal power of reactor by the theory of heat balance, which obtains thermal power (of generator) in second loop from primary loop through the measurement values of temperature, pressure, and flow rate in the second loop, counting the internal heat loss in at the same time. The advantages of the working conditions of second loop for easy measurement makes it an important method of obtaining thermal power of the doubleloop SCWR.
Figure 6 shows the heat in and out the system (expressed by arrows), which can be described by the following heat balance equation: where the is the core thermal power , is the thermal power obtained from the primary loop in the second loop in th steam generator, and is the thermal power coolant system obtained from other heat sources, , which can be estimated from the design of reactor.
The main physical process occurring in the steam generator is as follows: unsaturated water with the mass flow rate and specific enthalpy flows into the steam generator through the tube, exchanges heat with the coolant in primary loop, and mostly becomes wet steam with the mass flow and specific enthalpy ; after the increase of endothermic enthalpy, the others are the saturated blowdown water with mass flow rate and specific enthalpy . The thermal power in th steam generator can be calculated with following equation: where is the wet steam enthalpy in steam generator export, is the blowdown enthalpy, is the flow rate of blowdown in second loop, is the feedwater enthalpy in second loop, and is the flow rate of feedwater in second loop.
The feed water satisfies the law of conservation of mass as follows:
Simplify (13) and (14): where feedwater enthalpy and blowdown enthalpy are calculated by the thermodynamic properties subroutine, flow rate of feedwater can be obtained from flow rate calculation subroutine, and the flow rate of blowdown is a measured value.
The wet steam always consists of saturated steam and saturated water, which is determined by vapour fraction , so the enthalpy of wet steam is characterized by the following equation: where the is the enthalpy of saturated steam and is the enthalpy of saturated water; both are calculated by the thermodynamic properties subroutine.
3. Uncertainty Analysis of DoubleLoop SCWR
The relative uncertainty of thermal power given in (17) is obtained by the uncertainty transmission formula: where the is the uncertainty of thermal power in steam generation in each second loop and is the uncertainty of thermal power of coolant system in primary loop: where is the max uncertainty of each steam generation.
Assuming that
We can obtain the following equation:
3.1. The Calculation of
The following equation can be obtained by error propagation formula:
Assume that the uncertainty of saturated water in the wet steam is “1” as in (22) and inaccuracy of measurement should be in this range: Equation (22) can be deduced by the above formula:
is the uncertainty of saturated steam enthalpy, mainly caused by the uncertainty of pressure measurement and water and steam thermodynamic properties as follows: and the uncertainty caused by pressure measurement can be calculated by following equation: where is uncertainty caused by pressure measurement, root mean square of the uncertainty of pressure transmitter, data acquisition system, and calibration, determined by the design of pressure measurement: where is given in IAPWSIF97, and , , K, and kJ kg^{−1 }K^{−1}.
is the uncertainty caused by the calculation of water and steam thermodynamic properties, where can be selected in the corresponding section of IAPWSIF97.
3.2. The Calculation of
The uncertainty of saturated water enthalpy and feedwater enthalpy can be estimated by the method the same as mentioned above.
The relative uncertainty of mass flow rate can be described by the following equation:
The uncertainty of discharge coefficient is given by
If .12 mm, (10) should add the following term:
If and , the above values should add the following relative uncertainty:
The uncertainty of expansibility factor is , for compressible fluid, .
The uncertainty of internal diameter of the pipe line can be estimated by the following equation: where is the error of the measuring instrument; “2” is an extension coefficient of the confidence interval of 95%; is the constant of rectangular distribution.
The volume elasticity coefficient of water is quite large determining that its compressibility is very small, so the influence of pressure on the density can be ignored. The uncertainty of feed water density is determined by the uncertainty of temperature measurement and the calculation of water properties as follows: and the uncertainty caused by temperature measurement can be calculated by following equation:
The calculation procedures and method of the parameters are the same as the mentioned above.
The relative uncertainty of is estimated by experience values.
4. Validation of HPower Code
4.1. SingleLoop Type Program
We have done the verification of singleloop program in HPower using the main parameters design by Jacopo Buongiorno as in Table 2 and assuming the ideal and practical pump speed according to the level of pump speed at present.

The calculation result of thermal power 3564.3396 MW given in Table 3 shows a high consistency with the value 3575MW designed by US in Table 3.

4.2. DoubleLoop SCWR Program
Due to the lack of design data of SCWR, the validation of this part has been done by using the values of Qinshan Phase II [13] in Table 4 though it is not SCWR. Table 5 shows the comparison between the results of HPower and the values of Qinshan Phase II.


Although the main calculation result trend of SCWR is same as CNP650 of Qinshan Phase II, there is many detail differences in thermodynamic properties of water and steam and uncertainties calculation. The inconsistencies in Table 5 also come from the different input parameters in measuring instrument.
It is a valid way to verify the HPower while the main calculation process of both PWR and SCWR is the same and there is no particular data of SCWR fitting for the code. The result in Table 5 shows that HPower runs well and has a valid trend in thermal power and its relevance computation. So it can be used in SCWR design and calculation.
5. Conclusions
The thermal power calculation code HPower for SCWR was developed based on heat balance method, which can be easily applied in designs and operation. In this paper thermodynamic properties calculation subroutine based on IAPWSIF97 has been verified, and the uncertainty analysis has been proposed. The validation of HPower has been carried out in two parts: singleloop SCWR by the data given by Jacopo Buongiorno and doubleloop SCWR by the values of Qinshan Phase II. Although Qinshan Phase II is a PWR, the result can show that HPower is valid because the main calculation process of both PWR and SCWR is the same. In the future, the validation will be carried out using the values of SCWR when published.
Conflict of Interests
The authors declare that there is no conflict of interests regarding the publication of this paper.
References
 K. Dobashi, Y. Oka, and S. Koshizuka, “Conceptual design of a high temperature power reactor cooled and moderated by supercritical light water,” in Proceedings of the 6th International Conference on Nuclear Engineering (ICONE6 '98), San Diego, Calif, USA, 1998. View at: Google Scholar
 S. Shijia, “Calculation analysis of the heat balance test of l Ling Ao Nuclear Power Plant core power,” Chinese Journal of Nuclear Science and Engineering, vol. 25, pp. 271–277, 2005. View at: Google Scholar
 X. Yang, G. H. Su, W. Tian, J. Wang, and S. Qiu, “Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure condition,” Annals of Nuclear Energy, vol. 37, no. 12, pp. 1723–1734, 2010. View at: Publisher Site  Google Scholar
 X. J. Liu and X. Cheng, “Thermalhydraulic and neutronphysical characteristics of a new SCWR fuel assembly,” Annals of Nuclear Energy, vol. 36, no. 1, pp. 28–36, 2009. View at: Publisher Site  Google Scholar
 T. Reiss, G. Csom, S. Fehér, and S. Czifrus, “The simplified supercritical watercooled reactor (SSCWR), a new SCWR design,” Progress in Nuclear Energy, vol. 52, no. 2, pp. 177–189, 2010. View at: Publisher Site  Google Scholar
 B. Jacopo, “Progress report for the FY03 generationIV R&D activities for the development of the SCWR in the US,” US: INEEL, EXT0301210, 2003. View at: Google Scholar
 Y. Guodong and P. Zefei, “The analysis of qinshan second nuclear power plant power calibration method,” in Proceedings of the 12th Reactor Numerical Calculation and Particle Transport Academic Conference, Anhui, China, 2008. View at: Google Scholar
 The International Association for the Properties of Water and Steam , “Release on the IAPWS industrial formulation 1997 for the thermodynamic properties of water and steam,” Germany, 1997. View at: Google Scholar
 The 1967 IFC formulation for Industrial use, unrestricted publication allowed in all countries.
 P.H. Wang, J.Y. Jia, and M.H. Cheng, “The calculating models of water and steam properties with IAPWSIF97,” Power Engineering, vol. 20, no. 6, pp. 988–991, 2000. View at: Google Scholar
 ISO 5167, “Measurement of fluid flow by means of pressure differential devices inserted in circular crosssection conduits running full—part 2: orifice plate,” 2003. View at: Google Scholar
 William Fatoux, “A CANDUSCWR with a steam generator: preliminary thermodynamic assesment and estimation of fouling rates,” 2009. View at: Google Scholar
 B. Vogt, K. Fischer, J. Starflinger, E. Laurien, and T. Schulenberg, “Concept of a pressurized water reactor cooled with supercritical water in the primary loop,” Nuclear Engineering and Design, vol. 240, no. 10, pp. 2789–2799, 2010. View at: Publisher Site  Google Scholar
Copyright
Copyright © 2014 Fan Zhang et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.