OECD/NRC PSBT Benchmark: Investigating the CATHARE2 Capability to Predict Void Fraction in PWR Fuel Bundle

Abstract

Accurate prediction of steam volume fraction and of the boiling crisis (either DNB or dryout) occurrence is a key safety-relevant issue. Decades of experience have been built up both in experimental investigation and code development and qualification; however, there is still a large margin to improve and refine the modelling approaches. The qualification of the traditional methods (system codes) can be further enhanced by validation against high-quality experimental data (e.g., including measurement of local parameters). One of these databases, related to the void fraction measurements, is the pressurized water reactor subchannel and bundle tests (PSBT) conducted by the Nuclear Power Engineering Corporation (NUPEC) in Japan. Selected experiments belonging to this database are used for the OECD/NRC PSBT benchmark. The activity presented in the paper is connected with the improvement of current approaches by comparing system code predictions with measured data on void production in PWR-type fuel bundles. It is aimed at contributing to the validation of the numerical models of CATHARE 2 code, particularly for the prediction of void fraction distribution both at subchannel and bundle scale, for different test bundle configurations and thermal-hydraulic conditions, both in steady-state and transient conditions.

(ProQuest: ... denotes non-US-ASCII text omitted.)

A. Del Nevo 1 and D. Rozzia 2 and F. Moretti 2 and F. D'Auria 2

Recommended by Maria Avramova

1, ENEA UTIS-TCI, CR Brasimone, 40032 Camugnano, Italy
2, GRNSPG, University of Pisa, Largo Lucio Lazzarino 2, 56100 Pisa, Italy

Received 7 July 2012; Accepted 21 August 2012

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.

1. Introductory Remarks

A system code shall demonstrate that it is reliable in simulating and predicting the key phenomena of properly selected scenarios. This is a necessary prerequisite for its applicability in accident analysis aimed at demonstrating that a nuclear system is safe and unlikely to fail. The current generation of thermal-hydraulic system (TH-SYS) codes benefits decades of experience in experimental investigation and code development and qualification. They are considered mature tools to provide best estimate description of phenomena and detailed reactor system representation. However, there is still a large margin to improve and refine the modelling approaches taking advantage of more recent techniques that focus on microscopic mechanisms rather than on macroscopic effects, so that more accurate predictions can be obtained and reduction of uncertainties can be achieved. In this view, the qualification of the traditional methods (system codes) can be further enhanced by validation against high-quality experimental data (e.g., including measurement of local parameters), while in parallel more sophisticated 3D techniques (such as CFD) are developed and assessed. One of these databases, related to the void fraction measurments, is the pressurized water reactor subchannel and bundle tests (PSBT) conducted by the Nuclear Power Engineering Corporation (NUPEC) in Japan. Selected experiments belonging to this database are used for the OECD/NRC PSBT benchmark.

Prediction of void fraction and DNB in system thermal hydraulics is currently based on empirical approaches. Advancement in understanding and modelling complex flow behaviour in rod bundles would promote the validation of the current approaches and the development of more mechanistic approaches [ 1].

The aim of the activity is to assess the models of CATHARE2 (six-equation, two-field) code [ 2, 3] by means of void fraction measurements in subchannel configurations and in full scale bundle of Pressurized Water Reactor (PWR) at wide range of thermal-hydraulic boundary conditions (i.e., pressure, power, inlet temperature, and mass flow rate). In particular, the paper presents the results of four subchannel test sections and the analysis of three bundle configurations in steady-state and transient conditions. Sensitivity analyses are carried out addressing nodalization effect and the influence of the initial and boundary conditions of the tests.

2. The OECD/NRC NUPEC PSBT Experimental Database

The pressurized water reactor subchannel and bundle tests were conducted by NUPEC within an extensive experimental campaign aimed at verifying the reliability of fuel assemblies used for commercial nuclear power plants [ 4]. PSBT is able to simulate the high pressure, high temperature fluid conditions, which are typical of a PWR nuclear power plant (NPP).

The NUPEC test facility (Figure 1) consists of a high pressure and high temperature recirculation loop, a cooling loop, and instrumentation and data recording systems. The recirculation loop consists of a test section, circulation pump, preheater, steam drum (acting as a pressurizer), and a water mixer. The design pressure is 19.2 MPa, and the design temperature is 362°C. The operating conditions of the test facility are shown in Table 1.

Table 1: Range of NUPEC PWR test facility operating conditions.

Quantity	Range
Pressure	4.9-16.6 MPa
Mass velocity	550-4150 kg/m2 s
Inlet coolant temperature	140-345°C
Surface heat flux	37-186 W/cm2

Test sections of PWR subchannel and bundle tests.

(a) Test sections for sub-channel void distribution measurement

[figure omitted; refer to PDF]

(b) Test sections for rod bundle void measurement

[figure omitted; refer to PDF]

The void fraction tests include steady-state subchannel as well as steady-state and transient rod bundle experiments. Four subchannel test assemblies (TS 1, 2, 3, and 4) are used for measuring void fraction, as shown in Figure 1(a). They simulate the subchannel types (central, central with thimble, side, and corner) which are in a PWR assembly. The effective heated length is 1555 mm, and the void measurement section begins at 1400 mm from the bottom of the heated section. The overall subchannel database includes 126 tests, under a wide range of test conditions. Among these, 43 are carried out with TS 1, and TS 2 and 20 using TS 3 and TS 4 (see Figure 1(a)). Complete set of details about geometrical data, boundary conditions of the tests, and experimental results is available in [ 5].

The rod bundle test sections simulate a partial section and full length of a PWR fuel assembly. Figure 1(b)shows the test section used for the rod bundle void measurements. Three different bundles are used to perform the void distribution measurements (test sections B5, B6, and B7). The effective heated length is 3.618 m. Void fraction measures are available at three different elevations 2.216 m, 2.669 m, and 3.177 m, respectively. Steady-state tests were carried out for a wide range of operating conditions. Transient tests were executed increasing the void generation for power increase, flow rate reduction, depressurization, and coolant temperature increase. In these tests, thermal-hydraulic conditions comparable with typical scenarios were selected ranging from anticipated transients and postulated accidents. Complete set of details about geometrical data, boundary conditions of the tests, and experimental results is available in [ 5].

3. Thermal-Hydraulic Code Nodalizations

3.1. 1D Models of Subchannel and Bundle Test Sections

Rather simple 1D models were developed for simulating the four subchannel test sections. Here is a summary of the main features of the nodalizations [ 6, 7]:

(i) two BCONDIT components for imposing the boundary conditions of the tests (i.e., pressure, mass flow, and inlet temperature);

(ii) two VOLUME components, which simulate the inlet and the outlet of the test section;

(iii): one AXIAL component, which models the test section.

The electrical heaters of the subchannel and bundle test sections are modelled with WALL components. The linear power is imposed according to the specifications of the tests. The material properties implemented in the nodalization are provided by means of an external FORTRAN subroutine according to the specification in [ 5].

3.2. 3D Models of Bundle Test Sections

A nodalization of the bundle test section was also developed that takes advantage of the 3D modelling capabilities of CATHARE2. Here is a summary of the main features of the nodalization:

(i) two BCONDIT components for imposing the boundary conditions of the tests (i.e., pressure, mass flow, and inlet temperature);

(ii) two VOLUME components, which model the inlet and the outlet of the test section, and connected to the THREED component by means of two times 36 junctions;

(iii): a THREED component, having 1296 meshes, which provides a three-dimensional description of the bundle flow. It is discretized according to a Cartesian 6 ×6 pattern, so that one "cell" corresponds to one subchannel of the bundle and 36 axial nodes;

(iv) one equivalent heat structure (WALL) is defined for each subchannel;

(v) spacer grids are accounted for by equivalent pressure loss coefficients;

(vi) porosity is set at the junctions and at the volumes to account for the presence of the fuel pins and thus the real hydraulic flow areas;

(vii): turbulence option is activated.

4. Simulating the PSBT Facility Tests by CATHARE2 Code

The results of three different types of experiments [ 8] are discussed hereafter: (1) steady-state subchannel tests; (2) steady-state bundle tests; (3) transient bundle tests. Details of the boundary conditions of the tests are in [ 5, 8, 9].

4.1. Posttest Analysis of Steady-State Subchannel Tests

The analysis deals with 126 tests [ 8] related to the four test sections (see Figure 1(a)). Figure 2outlines the reference code results (labelled as "RUN1") in simulating the typical central subchannels (including the case with the thimble) and the other two test sections, referred to the side and corner geometries. Different colours are used to distinguish the four test series. Table 2provides information about the average absolute errors and the corresponding standard deviations for the various tests, grouped by void fraction ranges and by test series.

Table 2: Summary of subchannels results by CATHARE2 code.

Void fraction	TS 1	TS 2	TS 3	TS 4	Overall
Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number	Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number	Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number	Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number	Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number
0.0-0.05	0.005	0.0161	6	0.015	0.0092	5	0.013	0.0152	8	-0.004	0.0088	4	0.007	0.0143	23
0.05-0.10	-0.012	0.0244	9	-0.012	0.0264	6	--	--	--	-0.040	0.0132	4	-0.021	0.0251	19
0.10-0.15	-0.042	--	1	-0.040	0.0262	3	-0.002	0.0455	3	--	--	--	-0.028	0.0365	7
0.15-0.20	-0.023	0.0037	3	-0.079	0.0080	4	--	--	--	-0.091	0.0087	2	-0.064	0.0313	9
0.20-0.30	-0.081	0.0384	3	-0.030	0.0533	5	-0.102	--	1	-0.095	0.0200	3	-0.077	0.0485	12
0.30-0.40	-0.038	0.0574	8	-0.057	0.0490	5	-0.043	0.0496	2	-0.056	0.0080	2	-0.048	0.0477	17
0.40-0.60	-0.032	0.0757	7	-0.009	0.0520	10	-0.072	0.0759	4	-0.068	0.0143	3	-0.045	0.0633	24
0.60-0.80	0.007	0.0235	6	0.053	0.0267	5	--	--	--	-0.058	0.0021	2	0.000	0.0446	13
0.80-1.00	--	--	--	--	--	--	-0.107	0.0429	2	--	--	--	-0.107	0.0429	2

Figure 2: Overall subchannels tests (126 tests)--CATHARE2 v2.5_1 code, reference results.

[figure omitted; refer to PDF]

The results obtained for the 43 tests with Assembly S1 (TS 1, central subchannel) indicate a systematic underprediction of the void fraction (except at very low and high void fractions). The overall average absolute error on void fraction is -0.021, while the standard deviation is close to 0.05. The largest errors (about -0.08) are obtained for void fractions between 0.2 and 0.3 and for higher values of inlet coolant temperature and of system pressure (i.e., greater than 10 MPa).

Qualitatively similar results are obtained for Assembly S2 (TS 2, central subchannel with thimble). The same tendency to underprediction of void fraction is shown (except for void fractions below 0.1 and above 0.6). The average error is -0.016, and the standard deviation is 0.051. Up to void fraction 0.6, the standard deviation increases with the void fraction.

The results obtained for the 40 tests with Assemblies S3 and S4 (TS 3 and 4, side and corner subchannel) show the same tendencies as for the other tests, but with somewhat larger absolute errors (-0.03 and -0.05, resp.).

The results of the sensitivity calculations (Table 3) are summarized in Table 4and Figure 3. It appears that the average absolute error can be reduced from the reference results as the boundary conditions varied within the uncertainty of the experimental measurements. In particular, the most accurate prediction is achieved using the minimum mass flow rate as boundary condition. However, the dispersion of the results remains similar to that of the reference calculation and the underestimation of void fraction between 0.2 and 0.6 is only slightly improved.

Table 3: PSBT subchannel tests: list of reference and sensitivity calculations.

Test section	ID	Number of axial nodes	Pressure (1)	Mass flow (1)	Note
Steady-state subchannel	RUN1	100	Nominal	Nominal	Reference
RUN2	100	Nominal	Minimum	--
RUN3	100	Nominal	Maximum	--
RUN4	100	Minimum	Maximum	--
RUN5	100	Maximum	Nominal	--
RUN6	38	Nominal	Nominal	--
RUN7	16	Nominal	Nominal	Effect of pressure drop
C3	100	Nominal	Nominal	CATHARE3 (2) (same results are RUN1)

(1 ) Nominal: as specified in [ 5]. Minimum and maximum: according to the estimated accuracy of the measurement system.

(2 ) CATHARE3 is the new two-phase thermal-hydraulics system code developed at CEA to expand the capabilities of CATHARE2 (e.g., three field model, and turbulence transport for a continuous field or interfacial area transport for a dispersed field). CATHARE3 was applied against the PSBT data using the standard 6-equation model of CATHARE2. Thus, the task was a verification and a nonregression activity. The results are not reported here for sake of simplicity.

Table 4: PSBT subchannel tests, CATHARE2: summary of sensitivity analysis results.

Void fraction	TS 1	TS 2	TS 3	TS 4
Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number	Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number	Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number	Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number
RUN1 (refrence)	-0.021	0.0471	43	-0.016	0.0510	43	-0.030	0.0603	20	-0.054	0.0334	20
RUN2	-0.006	0.0489	43	-0.005	0.0493	43	-0.018	0.0617	20	0.044	0.0281	20
RUN3	-0.036	0.0474	43	-0.027	0.0537	43	-0.041	0.0610	20	-0.063	0.0402	20
RUN4	-0.010	0.0434	43	-0.006	0.0472	43	-0.019	0.0577	20	-0.043	0.0279	20
RUN5	-0.032	0.0512	43	-0.029	0.0534	43	-0.040	0.0637	20	-0.063	0.0391	20
RUN6	-0.018	0.0475	43	-0.014	0.0503	43	-0.028	0.0606	20	-0.052	0.0321	20
RUN7	-0.005	0.0500	43	-0.004	0.0488	43	-0.017	0.0622	20	-0.044	0.0276	20

Overall subchannels tests (126 tests)--sensitivity calculations.

(a) Test Series 1

[figure omitted; refer to PDF]

(b) Test Series 2

[figure omitted; refer to PDF]

(c) Test Series 3

[figure omitted; refer to PDF]

(d) Test Series 4

[figure omitted; refer to PDF]

The sensitivity analysis related to the number of axial meshes (RUNS6 and 7) shows some influence on the axial profile of the void fraction. Mesh convergence is already reached with 38 axial subdivisions, as the void fraction axial profile is very close to the more accurate reference solution (RUN 1). The effect is evidenced in Figure 4, where the void fraction of two tests is plotted as a function of height.

Test Series 1 (tests 1.5222 and 1.5223)--CATHARE2 code, nodalization effect.

(a) Test 1.5222

[figure omitted; refer to PDF]

(b) Test 1. 5223

[figure omitted; refer to PDF]

4.2. Posttest Analysis of Steady-State Bundle Tests

The experimental data consists of cross-sectional averages of the void fraction measured at three axial locations (bottom, middle, top) along the tests section height. The average, however, is not performed over the entire cross-section but only over the four central subchannels. This has to be taken into account for a proper comparison between numerical results and experimental data. Therefore, the results from the 3D models (Table 5) are also averaged according to the same procedure for comparison purposes. On the other hand, the results from the 1D models are inherently averaged over the entire cross-section and the comparison with the averaged experimental data would not in principle be appropriate.

Table 5: PSBT steady-state bundles (TS 5, TS 6, TS 7, TS 8,): summary of reference calculations results by CATHARE2 3D model.

Void fraction	TS 5	TS 6	TS 7	TS 8
Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number	Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number	Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number	Y9; [straight epsilon] [ α ] YA;	σ [ [straight epsilon] ]	Number
0.0-0.05	0.1003	0.0448	54	0.0931	0.0351	53	0.1031	0.0468	53	0.0469	0.0290	17
0.05-0.10	0.0895	0.0396	21	0.1074	0.0295	21	0.1068	0.0491	21	0.0425	0.0606	3
0.10-0.15	0.1017	0.0644	15	0.1511	0.0785	19	0.1310	0.0718	19	0.0102	0.0514	4
0.15-0.20	0.0801	0.0615	15	0.1408	0.0836	11	0.1323	0.0778	11	0.0392	0.0675	7
0.20-0.30	0.0464	0.0639	26	0.0951	0.0567	21	0.1134	0.0598	21	-0.0333	0.0783	10
0.30-0.40	0.0335	0.0568	27	0.0827	0.0541	33	0.1050	0.0741	33	-0.0344	0.0741	19
0.40-0.60	0.0827	0.0612	48	0.0946	0.0694	47	0.0603	0.0514	47	0.0144	0.0771	25
0.60-0.80	0.0256	0.0388	13	0.0253	0.0555	17	-0.0908	0.0796	17	0.0310	0.0285	8
0.80-1.00	--	--	0	--	--	0	-0.2784	--	0	--	--	0
0.0-1.00 (total)	0.061	0.0599	219	0.091	0.0651	222	0.082	0.0939	222	0.014	0.0675	93

The overall database includes 252 steady-state tests, as follows (see Figure 1(b)):

(i) 73 tests of test series 5--Assembly B5 (no thimble; uniform axial power profile),

(ii) 74 tests of test series 6--Assembly B6 (no thimble; cosinusoidal axial power profile),

(iii): 74 tests of test series 7--Assembly B7 (with thimble; cosinusoidal axial power profile),

(iv) 31 tests of test series 8--Assembly B5 (same as TS 5, i.e., no thimble; uniform axial power profile).

The details of the boundary conditions are reported in Table 1and [ 4, 5, 9].

Figure 5shows a comparison between the results obtained from the 3D model and the measured data, in terms of 4-subchannel cross-sectional averaged void fraction at the three available measurement locations (bottom, centre and top of the test section), for all 73 tests of test series 5 (Assembly B5, with uniform power profile). An annotation in the plot also indicates the absolute accuracy of the experimental data and the absolute error ±0.1 in terms of void fraction. Such results indicate that the void fraction is generally overpredicted in the 3D simulation. The figure includes the results from the 1D model. The latter are close to the results from 3D model (after averaging over the entire cross-sections), which confirms a consistency between the two models as far as the "integral" performance is concerned. Same qualitative trends, as for TS 5, are observed for the other two test bundles (as described in Figure 1(b)) in Figures 6and 7and for the test series 8 using the bundle B5 (Figure 8).

Figure 5: PSBT steady-state bundle (TS 5)--CATHARE2 3D and 1D models: central and bundle void fraction exp. versus calc., reference results.

[figure omitted; refer to PDF]

Figure 6: PSBT steady-state bundle (TS 6)--CATHARE2 3D and 1D models: central and bundle void fraction exp. versus calc., reference results.

[figure omitted; refer to PDF]

Figure 7: PSBT steady-state bundle (TS 7)--CATHARE2 3D and 1D models: central and bundle void fraction exp. versus calc., reference results.

[figure omitted; refer to PDF]

Figure 8: PSBT steady-state bundle (TS 8)--CATHARE2 3D and 1D models: central and bundle void fraction exp. versus calc., reference results.

[figure omitted; refer to PDF]

The analysis, based on 252 tests [ 8], shows generally reasonable (though overestimated) results of the 3D model (Table 5). Limitations are observed in calculating the average void fraction distribution in the central subchannels. According to the results of the test series 5, 6, and 7, the errors are approximately systematic in terms of absolute average void fraction in the range of 0-0.6. In particular, the void fraction is overestimated. For higher values (0.6-0.8), the errors are lower, and, in the case of TS 7, the code void fraction is largely underestimated. These results highlight that the cross flows from the inner towards the outer subchannels of the 3D model are underestimated by the code, until the void fraction is below 0.6.

The test cases with cosine power profile showed higher absolute errors than the uniform axial power profile tests. The code results of TS 8 evidence a good average accuracy. The results are centred across the experimental data and better than those of TS 5. It has to be remarked that TS 5 and TS 8 share the same geometrical configuration, and no difference is reported in the PSBT benchmark specifications. The comparisons with the 1D results highlight that the void fraction, in general, keeps being overestimated in subcooled boiling conditions. The activation of the turbulence model improves the accuracy of the results; nevertheless, it should be considered that it has not been developed for such kind of applications [ 8].

4.3. Posttest Analysis of Transient Bundle Tests

The behaviour of three bundle test sections (i.e., B5, B6, and B7) are simulated in transient conditions (i.e., power increase, pressure decrease, flow decrease, and coolant inlet temperature increase). The analysis deals with 12 transient tests [ 8] modelled with the 3D and 1D nodalizations (see Section 3). Hereafter the results of three out of twelve tests are reported for sake of simplicity (the overall results are available in [ 8]). They are (1) a flow reduction test with the bundle B5; (2) the coolant temperature at inlet increase test with the bundle B6; (3) the power increase test with the bundle B7.

The flow reduction test with the bundle B5 is characterized by the following constant boundary conditions: electrical power equal to 2250 kW, system pressure 15.1 MPa, coolant temperature at the inlet 302°C (subcooling 41°C). The experimental and calculated mass flow rate trends are reported in Figures 9(a)and 9(b)that show the time histories of both the calculated and the measured averaged void fractions for the three different measuring locations (as already discussed for the steady-state tests in Section 4.2). During the steady-state period that comes before the flow rate variation (reduction), a noticeable void fraction is predicted by the code at the upper location, while the measured value in the experiment is practically zero. This evidence is consistent with the results for steady-state tests, which also showed a general tendency to overpredict the void fraction in the central channels. On the other hand, the transient trends are rather well predicted, with a certain tendency to under estimation.

PSBT transient bundle tests (TS 5)--flow reduction--CATHARE2 3D: calc. versus exp., reference results (RUN131).

(a) mass flow rate versus time

[figure omitted; refer to PDF]

(b) void fraction versus time

[figure omitted; refer to PDF]

The coolant temperature increase test with the bundle B6 is performed at a system pressure of 15.4 MPa, electrical power equal to 2600 kW, and a constant mass flow rate of 8 kg/s. The coolant temperatures at inlet of the bundle have the trend reported in Figure 10(a), with a subcooling ranging from 49°C to 16°C. Figure 10(b)reports both the calculated and the measured averaged void fractions, for the three different measuring locations. The void fraction predicted at the top and middle locations before the beginning of the temperature rise is above the measured value. The increase in void fraction during the transient is predicted quite in advance and with smoother rates compared to the experiment. This is also connected with the position where the coolant temperature is measured: the thermocouple is upstream the test section. On the contrary, the boundary conditions in the calculation are set just below the fuel bundle. The maximum values of the predicted void fraction are comparable with the measured ones.

PSBT transient bundle tests (TS 6)--temperature increase--CATHARE2 3D: calc. versus exp., reference results (RUN131).

(a) coolant temperature at core inlet

[figure omitted; refer to PDF]

(b) void fraction versus time

[figure omitted; refer to PDF]

The power increase test with the bundle B7 has the following boundary conditions: the system pressure is equal to 15.5 MPa, the coolant temperature inlet is 288°C, corresponding to a subcooling of 57°C, and the mass flow rate is set to 8 kg/s. Figures 11(a)and 11(b)show the time histories of both the calculated and the measured bundle powers and averaged void fractions, for the three different measuring locations. At the top location, the increase in void fraction during the transient is predicted with a certain delay compared to the experiment (except for an earlier "disturbance"); then the calculated void fraction trend stabilizes at the same level as the measured one. On the other hand, the void fraction is noticeably overpredicted at the middle and bottom locations.

PSBT transient bundle tests (TS 7)--power increase--CATHARE2 3D: calc. versus exp., reference results (RUN131).

(a) Power versus time

[figure omitted; refer to PDF]

(b) void fraction versus time

[figure omitted; refer to PDF]

In general, the code assessment of CATHARE2 code against the PSBT transient bundle tests demonstrates satisfactory results obtained by the 3D model. In particular,

(i) a noticeable void fraction is predicted by the code at the upper location (and middle location in the temperature increase test, Figure 10), while the measured value is practically zero. This is consistent with the results observed in the steady-state tests;

(ii) good prediction of the maximum void fraction is in general calculated: exceptions are the few disturbances observed at the start of the transients.

5. Conclusive Remarks

This work dealt with the validation of CATHARE2 capabilities in predicting void fraction in convective boiling flows. The validation is performed using the experimental data from NUPEC, also involved in the OECD/NRC PSBT benchmark. Four subchannel and three bundle test sections are simulated in different thermal-hydraulic conditions (i.e., pressure, coolant temperature, mass flow, and power). The overall database includes steady-state and transient tests (i.e., pressure decrease, power increase, coolant inlet temperature increase, and mass flow rate decrease). Sensitivity analyses are carried out, which investigate the influence of number of nodes, different code option, initial and boundary conditions of the tests on the code predictions.

The analysis of 126 steady-state subchannel tests shows reasonable results for lower values of void fraction; underprediction for intermediate values of void fraction (i.e., 0.2-0.4) and good results for higher values.

(i) The void fraction is overestimated in subcooled boiling conditions. The opposite is observed in saturated boiling conditions (bubbly, slug, and churn flow regimes).

(ii) The sensitivity analysis demonstrates that the prediction can be improved by varying the boundary conditions of the simulations inside the range of their uncertainty.

(iii): The sensitivities addressing the effect of the number of nodes show the convergence of the mesh for number of nodes larger than 38.

The analysis of 252 steady-state bundle tests evidenced conservative (overestimated) results of the 3D model. In particular,

(i) limitations are observed in calculating the average void fraction distribution in the central subchannels (i.e., void dispersion connected with the cross flow). The errors are approximately systematic in terms of absolute average void fraction in the range of 0-0.6. In particular, the void fraction is overestimated. For higher values (0.6-0.8), the errors are lower, and, in the case of TS 7, the code void fraction is largely underestimated;

(ii) the test cases with cosine power profile showed higher absolute errors than the uniform axial power profile tests;

(iii): the code results of TS 8 evidence a good average accuracy. The results are centred across the experimental data. They are better than those of TS 5, which has the same geometrical configuration;

(iv) the comparisons with the 1D results confirm that the void fraction is, in general, overestimated in subcooled boiling conditions;

(v) the activation of the turbulence model improves the accuracy results. Nevertheless it should be considered that this option is not developed for such kind of applications.

The analysis of 12 transient bundle tests shows satisfactory results of the 3D model. In particular:

(i) A noticeable void fraction is predicted by the code at the upper location, while the measured value is practically zero. This is consistent with the results observed in the steady-state tests.

(ii) Good prediction of the maximum void fraction is in general calculated.

Nomenclature

α :

Void fraction

[straight epsilon] :

Average value

σ :

Standard deviation

1D:

1 dimensional

3D:

3 dimensional

CATHARE2:

Code for analysis of thermal-hydraulics during an accident of reactor and safety evaluation

CFD:

Computational fluid dynamic

DNB:

Departure from nucleate boiling

ENEA:

Agenzia nazionale per le nuove tecnologie, l'energia e lo sviluppo economico sostenibile

OECD:

Organization for Economic Co-operation and Development

NEA:

Nuclear Energy Agency

NPP:

Nuclear power plant

NRC:

Nuclear Regulatory Commission

NUPEC:

Nuclear Power Engineering Corporation

PSBT:

Pressurized water reactor subchannel and bundle tests

PWR:

Pressurized water reactor

TB:

Test bundle

TS:

Test series

UNIPI:

Università di Pisa.

Acknowledgments

The authors would like to acknowledge the OECD Nuclear Energy Agency (NEA) and the NRC that promoted the PSBT benchmark and the CATHARE Team (in particular, M. Valette and D. Bestion) for the kind and valuable technical support.

References

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[2] G. Lavialle CATHARE2 V2. 5 User Guidelines , SSTH/LDAS/EM/2004-067, CEA, Grenoble, France, 2005.

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[7] A. Del Nevo, L. Michelotti, D. Rozzia, F. Moretti, F. D'Auria, "Void fraction prediction of NUPEC PSBT Tests by CATHARE code," paper 415 in Proceedings of the NURETH-14, Ontario, Canada, September 2011.

[8] A. Del Nevo, F. Moretti, D. Rozzia, F. D'Auria, "Final report on modeling and validation of multi-field models, dynamic interfacial area and turbulence for LOCA conditions," EC FP7 NURISP Project , no. D-2. 4. 2. 10b Rev. 1, 2012.

[9] JNES, "OECD/NEA Benchmark Based on NUPEC PWR Sub-channel and Bundle Tests (PSBT). Assembly specification and benchmark database (Volume 1)," Japan Nuclear Energy Safety Organization (JNES) , no. SAE-TH08-0019, 2009.

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