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Special Section Papers

Assessment of RELAP5/MOD3.3 Against Single Rod Reflooding Experiments

[+] Author and Article Information
N. Lymperea

Department of Nuclear Engineering,
National Technical University of Athens,
Zografos Campus,
9 Heroon Polytechniou,
Athens 15780, Greece
e-mail: nlymper@mail.ntua.gr

A. Nikoglou

Department of Nuclear Engineering,
National Technical University of Athens,
Zografos Campus,
9 Heroon Polytechniou,
Athens 15780, Greece
e-mail: anikog@mail.ntua.gr

E. Hinis

Department of Nuclear Engineering,
National Technical University of Athens,
Zografos Campus,
9 Heroon Polytechniou,
Athens 15780, Greece
e-mail: ephinis@mail.ntua.gr

1Corresponding author.

Manuscript received January 31, 2017; final manuscript received September 3, 2017; published online December 5, 2017. Assoc. Editor: Mohammad Pourgol-Mohammad.

ASME J. Risk Uncertainty Part B 4(3), 030903 (Dec 05, 2017) (7 pages) Paper No: RISK-17-1008; doi: 10.1115/1.4037879 History: Received January 31, 2017; Revised September 03, 2017

This study presents an assessment of the RELAP5/MOD3.3 using the experimental work upon the rewetting mechanism of bottom flooding of a vertical annular water flow inside a channel enclosing concentrically a heated rod. The experiments have been carried out in the experimental rig 1 of the Nuclear Engineering Department of National Technical University of Athens (NTUA-NED-ER1) inside which the dry out and the rewetting process of a hot vertical rod can be simulated. Experiments have been conducted at atmospheric conditions with liquid coolant flow rate within the range of 0.008 and 0.050 kg·s−1 and two levels of subcooling 25 and 50 K. The initial average surface temperature of the rod for each experiment was set at approximately 823 K. The predicted rod surface temperatures during rewetting of the RELAP5/MOD3.3 calculations were compared against the experimental values. The results presented in this study show that RELAP5/MOD3.3 provides temperature estimations of the reflooding mechanism within acceptable marginal error. However, larger deviations between predicted and experimental values have been observed when subcooled water was used instead of saturated one.

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References

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Figures

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Fig. 1

Schematic diagram of the experimental facility

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Fig. 2

Schematic diagram of the heated rod with thermocouple positions in mm

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Fig. 3

Experimental temperature history of thermocouple stations TC3 to TC11 at conditions of saturation during a low mass flow rate of 0.025 kg·s−1 and initial wall temperature at 823 K

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Fig. 4

Experimental temperature history of thermocouple stations TC3 to TC11 at conditions of saturation during a high mass flow rate of 0.050 kg·s−1 and initial wall temperature at 823 K

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Fig. 5

Heated rod mesh points

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Fig. 6

Nodalization diagram for the reflooding tests

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Fig. 7

Effect of axial noding on bottom quench front elevation

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Fig. 8

Experimental and predicted temperature history of the thermocouple station TC10 concerning the experiments 14051030.14 using saturated coolant at 0.025 kg·s−1 mass flow rate

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Fig. 9

Experimental and predicted temperature history of the thermocouple station TC10 concerning the experiments 28051213.14 using saturated coolant at 0.050 kg·s−1 mass flow rate

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Fig. 10

Experimental and predicted temperature history of the thermocouple station TC10 concerning the experiments 07101413.14 using 25 K subcooled coolant at 0.050 kg·s−1 mass flow rate

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Fig. 11

Experimental and predicted temperature history of the thermocouple station TC10 concerning the experiments 30101101.14 using 50 K subcooled coolant at 0.050 kg·s−1 mass flow rate

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Fig. 12

Experimental and predicted temperature history using a time delay card of the thermocouple station TC10 concerning the experiment 28051213.14

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Fig. 13

Temperature deviations of nine thermocouple stations for four different experiments

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