# Temperature Dependence of Thermophysical Properties of Full-Scale Corium of Fast Energy Reactor

Authors: Mazhyn K. Skakov; Nurzhan Ye. Mukhamedov; Alexander D. Vurim; Ilya I. Deryavko
Journal: Science and Technology of Nuclear Installations
 (2017)

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## Abstract

For the first time the paper determines thermophysical properties (specific heat capacity, thermal diffusivity, and heat conductivity) of the full-scale corium of the fast energy nuclear reactor within the temperature range from ~30°С to ~400°С. Obtained data are to be used in temperature fields calculations during modeling the processes of corium melt retention inside of the fast reactor vessel.


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## Body

## 1. Introduction

Research of thermophysical properties of the materials and fuel of nuclear reactor at high temperatures is an important scientific problem of practical relevance. From the practical point of view data of thermophysical properties of the melt reactor core (corium) and its individual components are important for modeling the phenomena and processes being an integral part of hypothetical nuclear reactors severe disasters scenarios.It is known that thermophysical properties (TPP) of corium [1–4] got during the experiments simulating severe accidents in nuclear reactors are most important characteristics since the information about TPP is exclusively useful for revealing the mechanisms of severe reactor accidents. This is why it is necessary to study corium thermophysical properties experimentally to form database that can be used in computational models and to predict the way of severe accident.As part of the above research, the Institute of Atomic Energy (IAE) NNC RK conducts experiments at the IGR research reactor to study behavior of fast energy nuclear reactor fuel under the conditions of severe accident with loss of coolant (LOCA).The work is focused on experimentally determining TPP of full-scale corium (solidified mixture of uranium and steel dioxides) of fast energy reactor produced during one of such experiments at the IGR reactor.


## 2. Material and Methods

As an investigation material, an ingot of full-scale corium was obtained by irradiating an experimental device on an IGR reactor. The experimental device included a fuel assembly consisting of fuel pellets of uranium dioxide with enrichment of 17% at235U in the active part and 0.27% at 235U in the blanket part. The fuel claddings were made of steel tubes Cr16Ni15Mo3Nb. Foreign analogues of Cr16Ni15Mo3Nb steel are 318 (USA) and X10CrNiMoNb18-12 (Germany).Thermophysical properties of the obtained corium were measured on UTFI-2 laboratory installation. For determining TPP we used methodology in [5]. The main point of the methodology is heating one of the ends of the plane disc sample by short term exposure of heat pulse and registration of temporary dependence upon T=f(τ) temperature on the opposite sample end. We have used the measurement scheme with two samples one of which is a major (examined), and the other one is an auxiliary sample (Figure 1). We used a disk sample of sintered uranium dioxide as an auxiliary sample. Heat impulse was created by electric heater located between the researched and the auxiliary samples.Figure 1
Scheme of placing samples in UTFI-2 installation: 1: thermocouple; 2: heat insulation; 3: examined sample; 4: heating element; 5: auxiliary sample.Using this methodology it is necessary to obtain (Figure2) thermogram and with its help determine such sample parameters as ΔT overheat (the difference between the sample initial and maximum temperatures) and τ1/2 is the time of reaching half of the sample surface maximum temperature. These parameters allow calculating target value of such sample TPP as a, thermal diffusivity, Cp, specific heat capacity, and λ,heat conduction.Figure 2
The typical form of changing temperature fixed on the sample back surface.Research on structure and elemental composition of corium was conducted on JSM-6390 raster-electron microscope of JEOL Japan company equipped by JED-2300 energo dispersive microscope.X-ray structural corium researches were conducted on Empyrean diffractometer with Rentgen-Master controlling computer system using CuKα-radiation.X-rayograms were obtained by monochromated CuKα-radiation (λКα1=0.154056 nm) under accelerating voltage of 20 kV and anode current of 40 mA with scanning interval with angle of 2θ: 30°–120° and stride of 0.02°.X-rayogram transcript was carried out by Crystallography Open Database (COD). Quantity analysis was conducted by HighScore software. Presence of one or another phase was fixed if two more intensive lines were marked in X-rayogram.


## 3. Results and Discussion

Diffractogram analysis from sample surface detected uranium dioxide with face centered cubic lattice with evaluative parameter of latticea=0.547 nm (~99% on mass) as main crystal phase.On diffractograms of all samples main phase peaks are tight, with permittedKα1,2 doublet. The ratio of phase line intensity of all samples differs markedly from the ratio of lines intensity of this phase in database, indicating the presence of crystallite preferred orientation on samples.The result of research of light line intensity was the detection of phase line on the basis ofα-(Fe, Ni, Cr) ferrite. Fraction of metal contaminations in samples according to microstructure research results was at a level of 1.5–2.5%, and there was no considerable dispersion of fraction on sample surface. Elemental composition of contamination shows that main elements of its chemical composition are components of chrome-nickel stainless steel in decreasing order of Fe, Cr, Ni, Mo, and Mn.Sample surfaces structure is characterized by pore and fracture presence. There was large amount of fracture in samples, forming fracture network among them (Figure3).Figure 3
Surface structure cut from solidified melt.
(a)
Sample 1
(b)
Sample 2During sample microstructure research, metallic contaminations with dimensions of 2–8μm were detected (Figure 4), distribution characters of which are at different marks of solidified melt.Figure 4
Metallic contaminations in sample microstructure on magnification of×500.
(a)
Sample 1
(b)
Sample 2EDS analysis of each sample was carried out for elemental composition of solidified melt. Data on elemental composition in mass and atom per cents were shown in Tables1 and 2.Table 1
Elemental composition of researched sample surface in mass %.
Samples
U
Fe
Cr
O
Al
Ni
Ti
Nb
1
86.86
0.84
0.95
9.89
1.24
0.14
0.07
—
2
86.70
0.89
1.03
9.90
1.24
0.16
0.07
0.01Table 2
Elemental composition of researched sample surface in atom %.
Samples
U
Fe
Cr
O
Al
Ni
Ti
Nb
1
34.22
1.42
1.72
57.98
4.30
0.23
0.14
—
2
34.08
1.49
1.85
57.88
4.30
0.25
0.14
0.01Local elemental analysis was conducted for identification of elemental composition of metallic contaminations (Figure5 and Table 3).Table 3
Elemental composition of metallic contaminations on samples, mass %.
Analysis area
O
Al
Ti
Cr
Fe
Ni
Nb
U
6.1
—
1.04
0.87
62.04
30.39
3.73
—
1.93
6.2
0.43
0.86
0.66
52.25
38.97
5.42
0.23
1.18
7.1
—
0.62
0.19
29.67
61.47
6.25
0.68
1.12
7.2
—
0.86
0.49
48.70
45.02
4.92
—
0.02Figure 5
Local elemental analysis of metallic contaminations.
(a)
Sample 1
(b)
Sample 2Therefore, it was determined by local elemental analysis of metallic contaminations that contaminations predominantly consist of chrome and iron, and in this regard uranium content was about 1%.Table4 shows the results of measuring diameter d, thickness l, mass m, determining density ρ, and porosity ε of the samples material used in the measurements.Table 4
Results of sample parameter measurements.
Sample
l, mm
d, mm
m, g
ρ, g/сm3
ε, %
Number 1
4.08
±
0.01
10.77
±
0.10
3.822
±
0.001
10.3
±
0.19
6
±
1.7
Number 2
4.11
±
0.01
10.89
±
0.07
3.981
±
0.001
10.4
±
0.16
5
±
1.4
UО2
4.02
±
0.01
10.97
±
0.07
3.8715
±
0.0001
10.37
±
0.04
5
±
1.4Uranium dioxide TPP calibration measurements were done before the corium TPP measurements. Table5 shows the results of calibration measurements of the UО2 sample TPP inside the chamber.Table 5
The result of uranium dioxide sample measurements.
a, ·10−6m2/sec
C
p, J/(kg·К)
λ, W/(m·К)
2.413 ± 0.003
270 ± 1.0
6.69 ± 0.02Calibration measurements results have shown the correspondence within the error of measured TPP values defined under the working chamber conditions. Values obtained in the working chamber were taken as the basic ones for correction coefficient calculating. Table6 shows the reference values taken for the calculation and the coefficients calculating results. Table 7 shows results of calculating correction coefficients using reference data [6].Table 6
TPP values of the samples for UО2 samples series.
Sample
Temperature, °С
TPP coefficients
a, ·10−6 m2/sec
C
p, J/(kg·K)
λ, W/(m K)
UO2 (95%)
27
3.08
237
7.59
UO2 inside the chamber
28
2.413
269
6.69Table 7
Results of determining correction coefficients.
Sample
K
a
K
c
K
λ
Inside the chamber
1.296
±
0.005
0.893
±
0.008
1.17
±
0.012Table8 shows the results of TPP measurements of corium sample number 1 conducted during the measurements within the selected temperature range. The table shows the data taking into consideration the correction coefficients.Table 8
Results of temperature changes of sample number 1 TPP coefficients measurement.
Control measurements
Temperature, °С
Pulse energy, J
TPP coefficients
a, ·10−6m2/sec
C
p, J/(kg·K)
λ, W/(m·K)
1st cycle, heating
1
30.7 ± 0.7
13.52 ± 0.05
2.686 ± 0.005
228.4 ± 0.7
6.22 ± 0.03
2
112.4 ± 0.4
13.01 ± 0.08
2.41 ± 0.021
253 ± 1.2
6.19 ± 0.03
3
160 ± 1.1
12.79 ± 0.05
2.28 ± 0.018
270 ± 3.0
6.2 ± 0.11
4
197.3 ± 0.5
12.73 ± 0.09
2.152 ± 0.004
281 ± 1.9
6.13 ± 0.03
5
246.1 ± 0.3
12.48 ± 0.04
1.997 ± 0.006
291 ± 1.4
5.90 ± 0.05
6
247.9 ± 0.7
16.36 ± 0.08
2.01 ± 0.04
292.2 ± 0.5
6.0 ± 0.12
7
306.8 ± 1.1
16.1 ± 0.13
1.90 ± 0.04
307.0 ± 0.3
5.9 ± 0.13
1st cycle, cooling
8
259.8 ± 0.4
16.18 ± 0.04
1.953 ± 0.006
296 ± 2.5
5.86 ± 0.07
9
205.1 ± 0.4
12.58 ± 0.02
2.09 ± 0.013
286 ± 1.3
6.08 ± 0.05
10
67.8 ± 0.7
12.8 ± 0.12
2.516 ± 0.007
244 ± 1.2
6.22 ± 0.03
2nd cycle, heating
1
68.0 ± 0.7
13.03 ± 0.02
2.51 ± 0.011
246 ± 2.5
6.24 ± 0.09
2
96.2 ± 0.6
12.76 ± 0.05
2.44 ± 0.027
256 ± 1.4
6.33 ± 0.09
3
197.0 ± 0.8
12.59 ± 0.08
2.110 ± 0.004
286.3 ± 0.8
6.12 ± 0.01
4
304.0 ± 0.6
16.26 ± 0.02
1.844 ± 0.007
308 ± 1.8
5.76 ± 0.05
5
349 ± 1.2
15.98 ± 0.03
1.758 ± 0.007
319 ± 2.6
5.68 ± 0.02
6
399.5 ± 0.5
15.97 ± 0.05
1.638 ± 0.003
326 ± 1.4
5.42 ± 0.02
2nd cycle, cooling
7
346.4 ± 0.7
15.98 ± 0.03
1.713 ± 0.008
322 ± 3.1
5.59 ± 0.03
8
253 ± 1.6
16.57 ± 0.04
1.889 ± 0.006
297 ± 3.0
6.27 ± 0.07
9
143.2 ± 0.4
13.04 ± 0.09
2.128 ± 0.003
279.9 ± 0.2
6.04 ± 0.01
10
21.1 ± 0.4
13.20 ± 0.04
2.513 ± 0.009
237.7 ± 0.4
6.05 ± 0.02
3rd cycle, heating
1
68.0 ± 0.7
13.03 ± 0.02
2.51 ± 0.011
246 ± 2.5
6.24 ± 0.09
2
96.2 ± 0.6
12.76 ± 0.05
2.44 ± 0.027
256 ± 1.4
6.33 ± 0.09
3
197.0 ± 0.8
12.59 ± 0.08
2.110 ± 0.004
286.3 ± 0.8
6.12 ± 0.01
4
304.0 ± 0.6
16.26 ± 0.02
1.844 ± 0.007
308 ± 1.8
5.76 ± 0.05
5
349 ± 1.2
15.98 ± 0.03
1.758 ± 0.007
319 ± 2.6
5.68 ± 0.02
6
399.5 ± 0.5
15.97 ± 0.05
1.638 ± 0.003
326 ± 1.4
5.42 ± 0.02
3rd cycle, cooling
7
346.4 ± 0.7
15.98 ± 0.03
1.713 ± 0.008
322 ± 3.2
5.59 ± 0.03
8
253 ± 1.6
16.57 ± 0.04
1.889 ± 0.006
297 ± 3.3
6.27 ± 0.07
9
182.2 ± 0.4
13.04 ± 0.09
2.128 ± 0.003
279.9 ± 0.2
6.04 ± 0.01Results of TPP measurements of sample number 1 are well reproduced in the range of temperatures from 30°C to 300°С in the first cycle and during the heating in the second cycle.At the same time thermophysical properties dependence deviations became more significant after heating up to 400°С. Foremost, the thermal diffusivity values underwent changes. Thus, at the temperature of 100°С, thermal diffusivity in the second-cycle control measurements was decreased on 5%, heat capacity was increased on 2%, and heat conductivity was decreased on 4%.Additional cycle of heating-cooling up to 400°С was conducted for checking the assumption about the beginning of structural changes of the corium material due to heating. In the process of heating at control temperatures of 200°С and 400°С, samples were aged for an hour to reveal possible TPP changes with the course of time. Table8 shows the measurement results.Obtained coefficients values during the heating and cooling coincided quite accurately and practically reproduced the temperature dependence obtained during the cooling stage in the second heating cycle.Table9 shows the results of TPP measurements of corium sample number 2 conducted during the measurements within the selected temperature range. The table shows the data taking into consideration the correction coefficients.Table 9
The results of TPP measurements of corium sample number 2 within the temperature range from 30°C to 400°C.
Control measurements
Temperature, °С
Pulse energy, J
TPP coefficient
a, ·10−6m2/sec
C
p, J/(kg·K)
λ, W/(m·K)
1st cycle, heating
1
28.2± 0.2
13.96± 0.09
2.773± 0.004
239.2± 0.5
6.822± 0.004
2
52.1± 0.2
13.08± 0.02
2.73± 0.012
243.6± 0.6
6.85± 0.04
3
108.5± 0.9
12.67± 0.09
2.524± 0.009
252.9± 0.9
6.57± 0.05
4
154± 1.7
12.2± 0.19
2.385± 0.005
266± 1.2
6.53± 0.019
5
207.0± 0.6
12.15± 0.02
2.221± 0.005
281± 3.3
6.43± 0.08
6
206± 1.0
15.00± 0.09
2.21± 0.012
284± 1.5
6.44± 0.06
7
253.5± 0.9
15.1± 0.31
2.06± 0.013
288.9± 0.1
6.12± 0.04
8
304.6± 0.8
14.9± 0.12
1.93± 0.010
301± 3.2
5.99± 0.06
1st cycle, cooling
9
205± 1.2
15.57± 0.08
2.15± 0.011
284.1± 0.9
6.27± 0.05
10
150.7± 0.10
13.17± 0.04
2.34± 0.011
276± 1.1
6.65± 0.05
11
149.90± 0.04
16.09± 0.03
2.33± 0.052
271.1± 0.4
6.50± 0.02
12
102.8± 0.3
12.87± 0.08
2.514± 0.008
256± 1.8
6.63± 0.06
2nd cycle, heating
1
33.9± 0.9
13.58± 0.06
2.768± 0.006
235± 1.5
6.68± 0.03
2
99± 1.1
13.75± 0.05
2.51± 0.016
258± 2.4
6.67± 0.05
3
211± 2.0
13.52± 0.08
2.174± 0.001
286± 3.0
6.40± 0.07
4
297± 2.2
13.15± 0.04
1.953± 0.005
300± 2.1
6.03± 0.04
5
293.4± 0.6
16.20± 0.03
1.944± 0.009
299± 1.3
5.98± 0.05
6
341.8± 0.1
15.97± 0.05
1.850± 0.006
308.5± 0.5
5.87± 0.02
7
400± 1.7
15.5± 0.10
1.700± 0.004
316± 2.2
5.53± 0.02
2nd cycle, cooling
8
299.1± 0.3
15.91± 0.09
1.877± 0.007
305± 1.3
5.88± 0.04
9
202.6± 0.2
16.1± 0.12
2.07± 0.013
294± 1.6
6.27± 0.07
10
202.2± 0.3
13.1± 0.13
2.082± 0.007
293± 3.0
6.28± 0.08
11
103± 1.6
13.75± 0.04
2.345± 0.007
262± 3.4
6.32± 0.07
12
42.5± 0.4
13.37± 0.08
2.58± 0.016
245± 1.7
6.50± 0.08Results of TPP measurements of sample number 2 are well reproduced in the range of temperatures from 30°С to 300°С in the first cycle and during the heating of the second cycle. The TPP values measured in the beginning and end of the first cycle of heating differ in value not more than 3% for thermal diffusivity and heat capacity and not more than 5% for heat conductivity.Thermophysical properties deviation became more significant after heating up to 400°С. The thermal diffusivity values have changed first of all. Thus, at the temperature of 100°С the thermal diffusivity became 8% lower during the control measurement of the second cycle, heat capacity was increased on 4%, and heat conductivity was decreased on 6%.Results of TPP measuring of both corium samples have revealed the changing of thermal diffusivity and heat conductivity values after heating up to 400°С cycle. Here we should take into account the fact that the sample actual temperature could get higher temperatures especially from the side surfaces reacting on the temperature of the heating chamber walls.Figure6 shows the results of measuring TPP coefficients of the full-scale corium samples comparing with the results of calibration measurements of the uranium dioxide. Character of the obtained temperature dependencies of TPP coefficients coincides with the temperature dependencies obtained for uranium dioxide.Figure 6
Comparing the results of TPP measuring of full-scale corium and sintered uranium dioxide samples.
(a)
(b)
(c)The heat capacity and temperature dependence of samples heat capacity coincide within the range of 3% for both, the corium samples and uranium dioxide samples.Heat conduction and thermal diffusivity of the corium samples differ most, they are 10–15% lower than those of the uranium dioxide.TPP fixed changes after heating up to 400°С made the same 5–10% for the thermal diffusivity. Supposing that the difference of the material samples thermal diffusivity from the thermal diffusivity of the sintered uranium dioxide is mainly determined by the porosity and fracture we can suppose that the fracture parameters had to be changed significantly (two times approximately) for obtaining the similar effect.Measuring the samples geometric dimensions and mass has not revealed these parameters registered changes in the experiment result.


## 4. Conclusion

We have studied thermophysical properties of full-scale corium of the fast energy reactor obtained during the experiment on the IGR research reactor. Using the got results we have come to the following conclusions:(1)
Experimental data on TPP samples of full-scale corium of fast reactor in the temperature range from 30°C to~400°С was obtained for the first time.(2)
Well reproducibility of results was shown in the temperature range from 30°C to 300°С.(3)
Character of obtained temperature dependence of TPP sample coefficient of full-scale corium coincides with character temperature dependence, obtained for sintered uranium dioxide samples.



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