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Research Papers

Design of an In-Pile SCWR Fuel Qualification Test Loop

[+] Author and Article Information
Ales Vojacek

Research Centre Rez,
Hlavni 130, 250 68 Husinec-Rez, Czech Republic
e-mail: ales.vojace@ujv.cz

Mariana Ruzickova

Research Centre Rez,
Hlavni 130, 250 68 Husinec-Rez, Czech Republic
e-mail: mariana.ruzickova@cvrez.cz

Thomas Schulenberg

Mem. ASME
Karlsruhe Institute of Technology,
Kaiserstraße 12, 76131 Karlsruhe, Germany
e-mail: schulenberg@kit.edu

Manuscript received April 13, 2015; final manuscript received June 11, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.

ASME J of Nuclear Rad Sci 2(1), 011003 (Dec 09, 2015) (7 pages) Paper No: NERS-15-1054; doi: 10.1115/1.4030872 History: Received April 13, 2015; Accepted June 17, 2015

Abstract

In the development of the supercritical water-cooled reactor (SCWR), an in-pile fuel assembly test loop has been designed within the framework of the joint Chinese–European project, called SCWR-FQT (Fuel Qualification Test). This paper presents the basic design of the loop with its auxiliary and safety systems, which has been examined in detail by thermal-hydraulic analyses in order to achieve operation of the loop above the thermodynamic critical point of water (374°C, 22.1 MPa) and checked by stress analyses to assure safe operation. The designed experimental loop for fuel qualification in supercritical water consists of a closed pressurized water circuit with forced circulation of the coolant through the test section—the active channel which is intended to be installed into the existing research pool-type reactor LVR-15. The active channel will be operated at temperatures and pressures which are typical for the high-performance light water reactor (HPLWR). A thick-walled pressure tube made from austenitic stainless steel, which is able to withstand the high system pressure, encloses the active channel. It contains four fuel rods with $UO2$ (enrichment of 19.7% $U235$) with a total heating power of $∼64 kW$ and a recuperator in order to achieve hot channel conditions as they are expected to occur in the evaporator of the HPLWR. The internal flow is realized so as to prevent the creep condition of the pressure tube. An internal U-tube cooler serves as heat sink and is connected to the secondary circuit. The entire active channel is isolated from water of the reactor pool by an air gap between the pressure tube and an aluminum displacer. The test section with fuel is connected to a 300°C closed loop and to a primary pump located outside the reactor building as well as safety systems and auxiliary systems, such as purification and measurement circuits, which are all connected with the primary circuit.

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References

Buungiorno, J., and MacDonald, P. E., 2013, “Supercritical Water Reactor (SCWR) Progress Report for the FY-03 Generation-IVR&D Activities for the Development of the SCWR in the U.S.,” INEEL, .
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.
Ruzickova, M., Hajek, P., Vsolak, R., Berka, J., and Smejkalova, J., 2008, “New Experimental Loops for Research Reactor LVR-15,” Mater. Sci. Forum, 595–598, pp. 559–570.
Vojacek, A., 2009, “Design of the Active Channel of the SCWR-FQT Loop,” Master thesis, Czech Technical University, Prague, Czech Republic.
Schulenberg, T., Starflinger, J., Marsault, P., Bittermann, D., Maraczy, C., Laurien, E., Lycklama, J. A., Anglart, H., Andreani, M., Ruzickova, M., and Heikinheimo, L., 2009, “European Supercritical Water Cooled Reactor,” Seventh European Commission Conference on EuratomResearch and Training in Reactor Systems, FISA 2009, Karlsruhe Institute of Technology (KIT), Prague, Czech Republic.
Vojacek, A., 2012, “WP1 Interim Report After Year 1,” Research Centre Rez (CVR), Prague, Czech Republic, SCWR-FQT, Contract Number: 2669908.
Visser, D. C., Shams, A., Kiss, A., Vágó, T., Vojacek, A., and Frybort, O., 2013, “WP2 Analyses of Normal Operation,” Nuclear Research and Consultancy Group (NRG), Petten, SCWR-FQT, Contract Number: 2669908.
Schulenberg, T., Cheng, X. X. L., Zhou, Ch., Raqué, M., Zeiger, T., and Vojacek, A., 2014, “E3.3—Analysed of Design Basis Accidents,” Karlsruhe Institute of Technology (KIT), Karlsruhe, Germany, SCWR-FQT, Contract Number: 269908.
Schneider, R., Schlagenhaufer, M., and Schulenberg, T., 2010, “Conceptual Design of the Safety System for a SCWR Fuel Qualification Test,” Karlsruhe Institute of Technology (KIT), Shanghai, China, NUTHOS-08.
Vojacek, A., and Mazzini, G., 2014, “Analyses of the Start-Up and Shut-Down of SCWR Fuel Qualification Test,” Proceedings of the 22nd International Conference on Nuclear Engineering ICONE22, Research Centre Rez (CVR), Prague, Czech Republic.

Figures

Fig. 1

Overall model of the SCWR-FQT facility

Fig. 2

Technological scheme of the SCWR-FQT facility

Fig. 3

Drawing of the SCWR-FQT fuel rod

Fig. 4

Bottom plate (wing design)

Fig. 5

Spacer (support) of the fuel assembly

Fig. 6

Top part of the fuel assembly with disk springs and sketch of the compensation mechanism (right)

Fig. 7

Flow distribution in the active channel

Fig. 8

Cross section of the headpiece

Fig. 9

Cross section of the middle part of the active channel

Fig. 10

Cross section of the bottom part of the active channel

Errata

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