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809.1
Comparison of CFD and LP Codes for the Simulation of Hydrogen Combustion Experiments
Tadej Holler1, Ed M. J. Komen
2, Ivo Kljenak
1
1 Jožef Stefan Institute (JSI)
Jamova cesta 39
SI-1000, Ljubljana, Slovenia
[email protected], [email protected]
2 Nuclear Research and Consultancy Group (NRG)
Westerduinweg 3
1755 ZG, Petten, The Netherlands
ABSTRACT
With computational advances, many tools are available for researchers and engineers to
allow different approaches for their investigative work in nuclear safety. When considering
the hydrogen threat in severe accident analyses in nuclear power plants, particularly hydrogen
deflagration, mainly two approaches are being used, i.e. Lumped Parameter (LP) and
Computational Fluid Dynamics (CFD) codes. In this paper, a comparison of those two
approaches is performed based on three experiments performed in the THAI experimental
facility.
The results shown in this work indicate that more detailed analysis is obtainable using
the CFD approach. However, the LP approach is much better in obtaining some general
information about the hydrogen deflagration events while at the same time requiring
substantially less computational resources.
1 INTRODUCTION
During a postulated severe accident in a Light Water Reactor (LWR) Nuclear Power
Plant (NPP), hydrogen can be formed from steam, e.g. from zirconium-steam interaction [1].
When it is mixed with the surrounding air in the containment, it can form a highly flammable
mixture. Hydrogen combustion in NPP containment therefore poses a direct threat to the
relevant safety systems, structures and components and, most importantly, can even
compromise the containment integrity itself [1]. Such scenarios of hydrogen generation and
combustion inside a LWR NPP containment were confirmed in the Three Mile Island NPP
accident in the USA in 1979 [2] and in the Fukushima Daiichi NPP accident in Japan in
2011 [3]. In the latter, the destructive power of hydrogen combustion was demonstrated.
Despite the hydrogen mitigation systems installed to reduce the hydrogen risk, such as
Passive Auto-catalytic Recombiners (PARs) and igniters, reliable hydrogen risk assessment is
still required.
Mainly two types of codes are used for hydrogen safety analyses: a) lumped parameter
(LP) codes, e.g. ASTEC [4], CONTAIN [5], MELCOR [6], and SPECTRA [7] and b)
Computational Fluid Dynamics (CFD) codes, e.g. ANSYS Fluent [8], ANSYS CFX [9] and
COM3D [10]. LP codes provide relatively quick estimates of the pressure loads, while CFD
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Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
codes are much more CPU demanding, but offer a local-scale representation of the
phenomena involved.
In the nuclear research community, there is currently an ongoing debate about whether
CFD is really necessary to predict hydrogen deflagration phenomena occurring in real-scale
containments. This issue is often raised, since Lumped Parameter (LP) codes can predict the
mean maximum pressure 𝑝𝑚𝑎𝑥 or the Adiabatic Isochoric Complete Combustion (AICC)
pressure 𝑝𝐴𝐼𝐶𝐶 well in case of hydrogen combustion. However, during fast deflagrations,
intermediate peak pressures occur, which can be substantially higher than 𝑝𝐴𝐼𝐶𝐶. Estimation
of these maximum pressures is required in order to assess possible structural damage due to
hydrogen combustion.
Furthermore, the evaluation of possible structural damage of the containment does not
involve solely the maximum pressure, but the dynamic loads, e.g. rate of pressure change
versus time, must be considered as well. That is, in addition to the maximum pressure 𝑝𝑚𝑎𝑥 in
the containment, the rate at which the pressure increases with time, i.e. 𝑑𝑝 𝑑𝑡⁄ is important.
Also, the containment can undergo structural damage, if the residual pressure that remains
after complete burn oscillates with eigen frequencies corresponding to those of the
containment structure or the safety systems inside the containment. Therefore, both the
frequency and the amplitude of the pressure oscillations may also be important. This
essentially means that four parameters are important for the evaluation of the possible
structural damage: a) maximum pressure, b) rate of pressure increase 𝑑𝑝 𝑑𝑡⁄ , c) eigen
frequencies, and d) amplitudes corresponding to the residual pressure waves. The latter three
parameters cannot be obtained using an LP code, since these parameters depend on the flame
acceleration. This flame acceleration in turn depends on the generation of turbulence in the
flame front and the interaction of this flame with obstacles.
To show the importance of the effect of obstacles present, let us consider for example
experimental data obtained from the THAI and ENACCEF facilities. Such data were released
for CFD benchmarking in the OECD International Standard Problem No. 49 [11]. For a
similar gas composition, e.g. around 13 vol. % hydrogen concentration, the maximum flame
propagation velocity achieved in the THAI facility [12] was about 10 m/s, while in the
ENACCEF facility the maximum flame velocity reached almost 150 m/s (see Figure 1). That
is about an order of magnitude difference in the flame speed for almost the same gas
composition. This large difference in the flame propagation velocity is due to the turbulence
generated by the obstacles present in the ENACCEF facility. This turbulence generation leads
to increased flame acceleration.
Such flame acceleration due to turbulence generation by local obstacles cannot be
computed using LP codes. Furthermore, the propagation of the pressure wave phenomena
induced by the flame acceleration also cannot be computed by LP codes. Moreover, this
example demonstrated that no conclusions concerning flame propagation can be made based
on the evaluation of the gas mixture composition only. Basically, this is done when
conclusions are based solely on the usage of the frequently used Shapiro diagram [13]. The
considered local effects cannot be computed by LP codes, but can be computed by CFD
codes. However, such detailed CFD analyses consume substantially more resources than the
LP approach.
This paper focuses on comparison of results obtained only on experiments performed in
slow deflagration regime and described in more detail in the next section.
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Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
Figure 1: Axial flame propagation velocity observed in
THAI and ENACCEF experimental facilities.
2 EXPERIMENT
The THAI containment test facility, shown in Figure 2, is operated by Becker
Technologies GmbH in Eschborn, Germany. It is a vertical cylindrical stainless steel vessel
designed to withstand pressures of 20 bar at wall temperature 20 °C. The facility is measuring
9.2 m in height and 3.2 m in diameter, bringing the total volume to 60 m3. Within the
framework of the hydrogen deflagration (HD) part of the OECD-NEA THAI project [11,12],
29 different experiments were performed, aiming to provide a deeper insight into the
phenomenology of hydrogen deflagrations. In these experiments, varying initial conditions
were used, by changing the initial hydrogen and steam concentrations, temperature, pressure,
ignition location, and atmosphere stratification. During these experiments, all inner structures
that could possibly induce turbulence were removed, except for the experimental
instrumentation, which consisted of 43 thermocouples and 4 pressure transducers distributed
throughout the vessel.
For the purpose of this paper, three experiments with bottom ignition and different
hydrogen concentrations were selected. The initial conditions of these experiments are
presented in Table I.
Table 1: Initial conditions for considered THAI HD experiments
Hydrogen
concentration
[vol.%]
Temperature
[K]
Pressure
[kPa]
Mixture
THAI HD-12 8.0 291.0 148.5 Uniform
THAI HD-3 9.0 295.5 148.5 Uniform
THAI HD-7 9.9 290.0 148.0 Uniform
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Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
3 PHYSICAL AND NUMERICAL MODELING
3.1 Lumped Parameter Code – ASTEC
3.1.1 Physical modelling
The ASTEC code [6] is being jointly developed by the Institut de Radioprotection et de
Sûreté Nucléaire (IRSN – France) and the Gesellschaft für Anlagen- und Reaktorsicherheit
(GRS – Germany). To simulate hydrogen deflagration, the FRONT model in the ASTEC code
calculates the flame propagation from one control volume (into which the entire vessel is
divided during nodalisation) into adjacent ones. The flame propagation takes place within the
junctions of the system (flow connections between the volumes). The combustion of the gas
mixture takes place in the volumes and is calculated by a combustion model. The flame
propagates through junctions. At the end of each junction, it is checked whether the
conditions in the target zone are prone to ignition, based on the Shapiro diagram. In case the
ignition is possible, it occurs instantaneously or by user controlled boundary conditions – by
time or hydrogen concentration. After the combustion completeness criteria are reached, the
combustion stops. The laminar burning velocity is calculated according to the Liu-
MacFarlane correlation [14]. Turbulent flame front velocity is calculated via the Peters
correlation [15].
3.1.2 Nodalisation
In the input model for the ASTEC code, the THAI vessel was divided into 16 control
volumes (Figure 3). This nodalisation is a compromise between a much lower number, which
would not enable to simulate the gradual flame propagation in the axial direction, and a much
higher number of small volumes, for which lumped parameter codes were not developed.
Figure 2: Schematic of the THAI
experimental vessel.
Figure 3: Nodalisation of THAI
vessel for ASTEC code.
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Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
3.2 CFD Code – ANSYS Fluent
3.2.1 Physical modelling
The ANSYS Fluent CFD code [8] was used as a platform on which the combustion
model was implemented. The density-based coupled solver was applied together with an
explicit time stepping method. All spatial discretization schemes used were of second order.
The applied turbulence models were the standard 𝑘 − 𝜀 models.
In addition to the equations for conservation of mass, momentum and energy, the
additional transport equation for the Favre-averaged progress variable, �̃�, is resolved. This
progress variable is defined as:
�̃� =�̃�𝑓 − 𝑌𝑓,𝑢
𝑌𝑓,𝑏 − 𝑌𝑓,𝑢 (1)
Here, 𝑌𝑓 is the mass fraction of fuel, with indexes 𝑢 and 𝑏 representing the unburned
and burned states, respectively. Lipatnikov and Chomiak [16] proposed the following
progress variable transport equation for the Flame Speed Closure (FSC) combustion model:
𝜕�̅��̃�
𝜕𝑡+
𝜕�̅��̃��̃�𝑗
𝜕𝑥𝑗=
𝜕
𝜕𝑥𝑗[�̅�(𝜅 + 𝐷𝑡)
𝜕�̃�
𝜕𝑥𝑗] +
(𝑆𝑙)2
4(𝜅 + 𝐷𝑡)𝜌𝑢�̃�(1 − �̃�) + 𝜌𝑢𝑈𝑡|∇�̃�| (2)
In equation (2), 𝜅 and 𝐷𝑡 are molecular and turbulent diffusivities, respectively, 𝜌𝑢 is
the unburned gas density and 𝑆𝑙 represents the laminar flame speed. The third term on the
right hand side of the equation (2) is the quasi-laminar source term for progress variable, with
which the Turbulent Flame Speed Closure (TFC) combustion model [17], developed by
Zimont for fully turbulent premixed flames, was expanded by Lipatnikov and Chomiak. The
turbulent burning velocity 𝑈𝑡 is modeled, based on the work by Zimont, as follows:
𝑈𝑡 = 𝐴𝑢′𝐷𝑎1 4⁄ 𝐹(𝐿𝑒) (3)
Here, 𝐴 is a model constant, 𝑢′ is the turbulent intensity and 𝐷𝑎 is the Damkohler
number. It should be noted here that the model constant 𝐴 = 0.4 was the same for all the
considered computations. This follows the procedures from the previous FSC model
validations [18-20]. The preferential diffusion thermal (PDT) instabilities were accounted for
using the 𝐹(𝐿𝑒) term [18]. In the planar, fully developed case, the added source term results
in the simple expression for the flame speed, 𝑆𝑡:
𝑆𝑡 = 𝑆𝑙 + 𝑈𝑡 (4)
3.2.2 Mesh and boundary conditions
To obtain accurate results, while maintaining computational times at reasonable levels,
an adaptive mesh refinement (AMR) technique was applied to the flame front. A grid
sensitivity study was performed in an earlier work [18-20], which indicated that using two
levels of AMR produces practically grid independent results. Each level of refinement means
halving the size of a computational cell in every direction of the axisymmetric 2D model used
in our calculations. The base mesh cell size was around 2 cm by 2 cm, while the ignition
region was further refined to contain cells measured approximately 0.6 mm by 0.6 mm, to
keep the shape of the ignition region as even as possible. The ignition, located 1.55 m above
the floor of the vessel, was modelled with an ignition sphere with 8 cm radius, to which
burned properties were prescribed. The flame front position was extracted from the
809.6
Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
coordinates corresponding to the iso-surface value of c = 0.5, as done in our previous work
[18-20]. In the experiment, the reactants in the experiment were mixed using recirculation
fans and then switched off several minutes prior to the ignition. Thus, the initial turbulence
values were assumed to be low, although no measurements of these parameters were
performed. Initial values for k and ε were selected as 10-4 m2s-2 and 4.8·10-5 m2s-3,
respectively, throughout the computational domain. This is also done in accordance with the
previously conducted validations with the CFD-based modelling [18-20].
For slow deflagration computations in our previous work [18-20] it was shown that
complete heat transfer mechanism, including radiation, has a significant impact on total
energy levels and consequently on the pressure build-up. Therefore, the simulation results
were computed using prescribed constant wall temperature along with the Discrete Ordinates
(DO) thermal radiation model [8].
4 RESULTS AND DISCUSSION
With increasing initial hydrogen concentration, the trends of increasing pressure peak,
faster flame propagation and consequently higher pressure increase rate were observed in
experiments. Obtained simulation results with both LP and CFD approach are compared to
corresponding experiments HD-12, HD-3, and HD-12, by observing the pressure, axial flame
propagation and pressure increase rate 𝑑𝑝 𝑑𝑡⁄ .
4.1 Pressure
From the point of view of nuclear safety, the accurate prediction of the maximum (peak)
pressure that is reached during combustion is essential. Experimental and calculated pressures
are shown in Figures 4, 5, and 6, for cases HD-12, HD-3 and HD-7, respectively.
The overall observation is that both LP and CFD simulations provided adequate results
of maximum pressure. The trend of maximum pressure increase with increasing initial
hydrogen concentrations, as observed in the experimental results, was also reproduced
qualitatively well by both LP and CFD codes. Relatively mild pressure oscillations were
observed in the experiments with higher initial hydrogen concentrations, i.e. HD-3 and HD-7,
which were not captured by the CFD approach based on the described combustion modeling,
due to numerical dissipation (and were not expected to be captured by LP codes anyway).
However, it should be noted here, that the CFD modelling approach has already shown to be
capable of capturing the pressure oscillations during combustion [20].
Figure 4: Experimental and calculated pressure for run HD-12 (8.0 vol.% H2).
809.7
Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
Figure 5: Experimental and calculated pressure for run HD-3 (9.0 vol.% H2).
Figure 6: Experimental and calculated pressure for run HD-7 (9.9 vol.% H2).
4.2 Axial Flame Propagation
Experimental and calculated axial flame propagations are shown in Figures 7, 8, and 9,
for cases HD-12, HD-3 and HD-7, respectively. A trend of flame propagation rate increase
with increasing initial hydrogen content can be observed in the experiment. However, some
slowdown of flame propagation can be observed in CFD simulations with the flame
approaching the top of the vessel, especially in Figure 9. This rather peculiar flame behavior
can be attributed to the movement of the flame front towards the side of the vessel. The
observed “step” indicates the moment the flame touches the side wall, after which the
movement of the flame is again more intense in the axial direction.
As to the results obtained with the LP code, they are similar for all three considered runs
and, what is more important, very different from the experimental curves. This is a
consequence of the very simple modelling of flame propagation using the LP approach.
809.8
Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
Figure 7: Experimental and calculated axial flame propagation
for run HD-12 (8.0 vol.% H2).
Figure 8: Experimental and calculated axial flame propagation
for run HD-3 (9.0 vol.% H2).
Figure 9: Experimental and calculated axial flame propagation
for run HD-7 (9.9 vol.% H2).
809.9
Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
4.3 Pressure Increase Rate
For an easier interpretation of the pressure increase from pressure history results,
experimental and calculated pressure increase rates are shown in Figures 10, 11, and 12, for
cases HD-12, HD-3 and HD-7, respectively. Namely, both the maximum pressure and the
pressure increase 𝑑𝑝 𝑑𝑡⁄ development are considered highly important parameters for analysis
of the structural integrity of the NPP containment.
For the case HD-12, the CFD simulation overpredicts the maximum 𝑑𝑝 𝑑𝑡⁄ compared to
the experimental results for almost 50%, whereas the LP simulation overpredicts it only
slightly. However, in cases with higher initial hydrogen concentrations, i.e. HD-3 and HD-7,
the CFD simulations underpredict the experimental results by around 50% and 30%,
respectively. In the case HD-3, the LP simulation also underpredicts the maximum (albeit less
than the CFD simulation), whereas in the case HD-7, it overpredicts it.
As already shown in Figures 4-6, the simulations are capable of capturing the trend of
the earliest occurrence of first pressure increase, with the increase of initial hydrogen
concentration. For CFD simulations, this cannot be said for the trend of maximum 𝑑𝑝 𝑑𝑡⁄
values, since this parameter in simulation run of HD-12 is reached before the maximum of
case HD-3, which has a higher initial amount of hydrogen. For LP simulations, these
differences are too small to be considered.
Figure 10: Experimental and calculated pressure increase rate 𝑑𝑝 𝑑𝑡⁄
for run HD-12 (8.0 vol.% H2).
809.10
Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
Figure 11: Experimental and calculated pressure increase rate 𝑑𝑝 𝑑𝑡⁄
for run HD-3 (9.0 vol.% H2).
Figure 12: Experimental and calculated pressure increase rate 𝑑𝑝 𝑑𝑡⁄
for run HD-7 (9.9 vol.% H2).
5 CONCLUSIONS
For the case of slow hydrogen deflagration, considered in the present paper, results of
pressure and pressure increase rate calculated with the LP code are just as adequate, if not
even more, than results calculated with the CFD code. From the point of nuclear safety,
simulations with LP code appear to be sufficient, making lengthy simulations with CFD codes
unnecessary.
However, the comparison of calculated flame propagations with LP and CFD codes
clearly confirms, that LP codes do not simulate the basic mechanisms of combustion. Thus,
the reliability of results calculated with LP codes may be questionable for conditions for
which they have not been validated due to lack of suitable experimental data. In such cases,
CFD codes could be trusted more, as they solve the basic equations of fluid mechanics. Thus,
in the long term, the authors recommend the further development of CFD codes to improve
their predictions of pressure increase rate as well as to increase their calculation speed by
using efficient numerical methods.
ACKNOWLEDGMENTS
The work described in this paper was funded by the Dutch Ministry of Economic
Affairs, the Slovenian Research Agency (Research programme “Reactor Engineering”) and
the European Commission (CESAM project, 2013-2017).
REFERENCES
[1] I. Kljenak, A. Bentaib, T. Jordan, 2012. Hydrogen behavior and control in severe
accidents, in: Nuclear Safety in Light Water Reactors, B. R. Sehgal ed., pp. 186-227,
Elsevier, 2012.
[2] “Report of the President’s Commission on The Accident at Three Mile Island”, U.S.
Government Printing Office, Washington D.C., USA, 1979.
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Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
[3] “Fukushima Daiichi: ANS Committee Report”, American Nuclear Society Special
Committee, Illinois, USA, 2012.
[4] N. Reinke, CPA Module of ASTEC Programme Reference Manual, ASTEC-
V2/DOC/15-03 DRAFT Version Rev 1, Gesellschaft fur Anlagen- und
Reaktorsicherheit (Germany) and Institut de Radioprotection et de Surete Nucleaire
(France), 2015.
[5] K.K. Murata et al., “Users manual for CONTAIN 2.0: a computer code for nuclear
reactor containment analysis”, NUREG/CR-6533, Sandia National Laboratories, USA,
1997.
[6] R.M. Summers et al., “MELCOR 1.8.0: A computer code for nuclear reactor severe
accident source term and risk assessment analyses”, Sandia National Laboratories,
USA, 1991.
[7] M. Stempniewicz, “SPECTRA sophisticated plant evaluation code for thermal-
hydraulic response assessment version 3.60”, K5024/10.101640, NRG, The
Netherlands, 2009.
[8] ANSYS-Fluent Inc., Fluent 12.0. Lebanon, N.H., 2008.
[9] ANSYS CFX, “ANSYS CFX-10.0 users manual”, 2007.
[10] A.A. Efimenko, S.B. Dorofeev, “CREBCOM code system for description of gaseous
combustion”, Combustion, Explosion and Shock Waves, vol 14 (6), pp. 575-581, 2001.
[11] OECD/NEA report, “ISP-49 on Hydrogen Combustion”, NEA/CSNI/R(2011)9, 2012.
[12] T. Kanzleiter and G. Langer, “Hydrogen deflagration tests in the THAI test facility”,
2010.
[13] Z.M. Shapiro, T.R. Mofette, “Hydrogen flammability data and application to PWR loss-
of-coolant accident”, WAPD-SC-545, Pittsburgh, Pennsylvania, USA, 1957.
[14] D.D.S. Liu, R. MacFarlane, “Laminar burning velocities of hydrogen–air and
hydrogen–air–steam flames”, Combustion and Flame 49, pp. 59-71, 1983.
[15] N. Peters, Turbulent Combustion, Cambridge University Press, 2004.
[16] A.N. Lipatnikov, J. Chomiak, “Turbulent flame speed and thickness: phenomenology,
evaluation, and application in multi-dimensional simulations”, Progress in Energy and
Combustion Science, vol. 28, no. 1, pp. 1-74, 2002.
[17] V.L. Zimont, “Theory of turbulent combustion of a homogenous fuel mixture at high
Reynolds number”, Combustion, Explosion and Shock Waves, vol. 15, pp. 305–311,
1979.
[18] P. Sathiah, E. Komen, D. Roekaerts, “The role of CFD combustion modeling in
hydrogen safety management—Part I: Validation based on small-scale experiments”,
Nuclear Engineering and Design, vol. 248, pp. 93-107, 2012.
[19] P. Sathiah, T. Holler, I. Kljenak, E. Komen, “The role of CFD combustion modeling in
hydrogen safety management-V: Validation for slow deflagrations in homogeneous
hydrogen-air experiments“, Nuclear Engineering and Design, 2016, in press,
http://dx.doi.org/10.1016/j.nucengdes.2016.06.030
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Proceedings of the International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 5-8, 2016
[20] P. Sathiah, E. Komen, D. Roekaerts, “The role of CFD combustion modeling in
hydrogen safety management—Part II: Validation based on homogeneous hydrogen–air
experiments”, Nuclear Engineering and Design, vol. 252, pp. 289-302, 2012.