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Research Papers

Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor

[+] Author and Article Information
Csaba Maráczy

Centre for Energy Research, Hungarian Academy of Sciences,
1525 Budapest 114, P.O. Box 49, 1121 Budapest, Hungary
e-mail: csaba.maraczy@energia.mta.hu

György Hegyi

Centre for Energy Research, Hungarian Academy of Sciences,
1525 Budapest 114, P.O. Box 49, 1121 Budapest, Hungary
e-mail: gyorgy.hegyi@energia.mta.hu

István Trosztel

Centre for Energy Research, Hungarian Academy of Sciences,
1525 Budapest 114, P.O. Box 49, 1121 Budapest, Hungary
e-mail: istvan.trosztel@energia.mta.hu

Emese Temesvári

Centre for Energy Research, Hungarian Academy of Sciences,
1525 Budapest 114, P.O. Box 49, 1121 Budapest, Hungary
e-mail: emese.temesvari@energia.mta.hu

1Corresponding author.

Manuscript received April 1, 2015; final manuscript received June 17, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.

ASME J of Nuclear Rad Sci 2(1), 011004 (Dec 09, 2015) (5 pages) Paper No: NERS-15-1041; doi: 10.1115/1.4030933 History: Received April 01, 2015; Accepted June 26, 2015

The aim of the supercritical water reactor-fuel qualification test (SCWR-FQT) Euratom-China collaborative project is to design an experimental facility for qualification of fuel for the supercritical water-cooled reactor. The facility is intended to be operated in the LVR-15 research reactor in the Czech Republic. The pressure tube of the FQT facility encloses four fuel rods that will operate in similar conditions to the evaporator of the HPLWR reactor. This article deals with the three-dimensional (3D) coupled neutronic-thermohydraulic steady-state and transient analysis of LVR-15 with the fueled loop. Conservatively calculated enveloping parameters (e.g., reactivity coefficients) were determined for the safety analysis. The control rod withdrawal analysis of the FQT facility with and without reactor SCRAM was carried out with the KIKO3D-ATHLET-coupled dynamic code.

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References

Ruzickova, M., Schulenberg, T., Visser, D. C., Novotny, R., Kiss, A., Maraczy, C., and Toivonen, A., 2014, “Overview and Progress in the European Project: “Supercritical Water Reactor—Fuel Qualification Test”,” Prog. Nucl. Energy, 77, pp. 381–389. 10.1016/j.pnucene.2014.01.011
Ruzickova, M., Vojacek, A., Schulenberg, T., Visser, D. C., Novotny, R., Kiss, A., Maraczy, C., and Toivonen, A., 2015, “European Project Supercritical Water Reactor—Fuel Qualification Test (SCWR-FQT): Overview, Results, Lessons Learnt and Future Outlook,” Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-7), VTT Technical Research Centre of Finland Ltd, Helsinki, Finland, Mar.15–18 Paper No. ISSCWR7-1054.
Keresztúri, A., Hegyi, Gy., Korpás, L., Maráczy, Cs., Makai, M., and Telbisz, M., 2010, “General Features and Validation of the Recent KARATE-440 Code System,” Int. J. Nucl. Energy Sci. Technol., 5(3), pp. 207–238. 10.1504/IJNEST.2010.033476
Hegedűs, Cs., Hegyi, Gy., Hordósy, G., Keresztúri, A., Makai, M., Maráczy, Cs., Telbisz, F., Temesvári, E., and Vértes, P., 2002, “The KARATE Program System,” Proceedings of the PHYSOR 2002, Seoul, Korea, Oct. 7–10, American Nuclear Society, Inc., La Grange Park, IL.
Maráczy, Cs., Hegyi, Gy., Trosztel, I., Hordósy, G., and Brolly, A., 2014, “RIA Analysis of the SCWR-FQT Facility in the LVR-15 Research Reactor,” The 19th Pacific Basin Nuclear Conference, Vancouver, Canada, Aug. 24–28, Canadian Nuclear Society, Ottawa, ON.
Keresztúri, A., Hegyi, Gy., Maráczy, Cs., Panka, I., Telbisz, M., Trosztel, I., and Hegedűs, Cs., 2003, “Development and Validation of the Three-Dimensional Dynamic Code—KIKO3D,” Ann. Nucl. Energy, 30(1), pp. 93–120. 0306-4549 10.1016/S0306-4549(02)00043-9
Maráczy, Cs., Keresztúri, A., Trosztel, I., and Hegyi, Gy., 2010, “Safety Analysis of Reactivity Initiated Accidents in a HPLWR Reactor by the Coupled ATHLET-KIKO3D Code,” Prog. Nucl. Energy, 52(2), pp. 190–196. 10.1016/j.pnucene.2009.06.005
Keresztúri, A., Maráczy, Cs., Hegyi, Gy., Trosztel, I., and Pataki, I., 2008, “Safety Analysis of Reactivity Initiated Accidents (RIA) and Anticipated Transients Without SCRAM (ATWS) of the Budapest Research Reactor,” RRFM 2008 Transactions, Hamburg, Germany, Mar. 2–5, European Nuclear Society, Brussels, Belgium, pp. 122–132.

Figures

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Fig. 1

MCNP model of the FQT test section

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Fig. 2

MCNP model of the LVR-15 core with numbered core arrangement: control rods (1–8), automatic rod (9), and safety rods (10–12)

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Fig. 3

GLOBUS burn-up calculation for the LVR-15 reference core with 30% burnt IRT-4M assemblies next to the FQT section. Critical control rod positions in the LVR-15 core

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Fig. 4

Predicted power profile in the FQT test-section. GLOBUS burn-up calculation for the LVR-15 reference core with 30% burnt IRT-4M assemblies next to the FQT section

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Fig. 5

Power profile calculated with GLOBUS for the LVR-15 reference core at different core arrangements

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Fig. 6

Clad surface temperatures of the FQT fuel pins in 11 layers (2–12)

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Fig. 7

Fuel centerline temperatures of the FQT fuel pins in 11 layers (2–12)

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Fig. 8

Power curve of the FQT test section

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Fig. 9

Coolant temperatures in the FQT primary loop

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Fig. 10

Coolant pressures in the FQT primary loop

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Fig. 11

Clad surface temperatures of the FQT fuel pins in six layers (2–12)

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Fig. 12

Fuel centerline temperatures of the FQT fuel pins in six layers (2–12)

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Fig. 13

Reactivity of the LVR-15 research reactor during ATWS

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Fig. 14

Total power of the LVR-15 research reactor during ATWS

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Fig. 15

Maximum fuel centerline temperatures of the FQT fuel pins during ATWS

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