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2-Day Private Sightseeing City Tour of Moscow with Subway Excursion, Tsaritsyno and Novodevichy Monastery and 4-course Traditional Russian Lunch with Vodka Plus Russian Classic Ballet Evening provided by U Visit Russia

Study of modified VVER and typical PWR fuel in the HBWR reactor (Norway)

• Published: 21 December 2012
• Volume 113 , pages 171–178, ( 2013 )

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• B. Yu. Volkov 1 ,
• W. Wiesenack 1 ,
• V. V. Yakovlev 2 ,
• E. P. Ryazantsev 2 ,
• A. K. Panyushkin 3 ,
• A. V. Ivanov 3 ,
• O. V. Kryukov 3 ,
• P. I. Lavrenyuk 4 &
• Yu. V. Pimenov 4  

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Two experiments studying the standard and modified VVER fuel fabricated at the Machine-Building Plant (in Elektrostal) and PWR fuel produced according to the typical specifications were performed on the HBWR research reactor (Halden, Norway) from 1995 to 2005. The objective of these experiments was to study the effect of the structural-technological parameters on the behavior of VVER fuel in comparison with the typical PWR fuel. These studies made it possible to expand the in-reactor data base on the behavior of VVER uranium oxide fuel as well as to develop recommendations for improving the technology of its production in order to increase fuel stability under irradiation.

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Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor

M. V. Kormilitsyn, L. A. Kormilitsyna, … T. D. Shchepetina

PWR Fuel Cycle Increased Enrichment, Combination of Burnable Absorbers

Confirmation of the design characteristics of the tvs-k design after operation in the pwr reactor at ringhals-3 npp.

B. Yu. Volkov, E. P. Ryazantsev, V. V. Yakovlev, et al., “Studies of the behavior of VVER and PWR irradiated in the HBWR reactor (Halden, Norway),” At. Énerg. , 111 , No. 6, 342–348 (2011).

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B. Volkov, E. Ryazantzev, and V. Yakovlev, The Thermal and Mechanical Behaviour of Modified WWER Fuel Compared with PWR Specification Fuel in IFA-503.2 , HWR-637, December 2000.

B. Volkov and T. Tverberg, “Irradiation performance of modified WWER fuel compared with typical PWR fuel in the Halden Reactor Test,” in: 4th Int. Conf. on WWER Fuel Performance, Modelling, and Experimental Support , Bulgaria, Varna, Oct. 15, 2001, pp. 186–196.

B. Volkov and E. Kolstad, “Review of WWER fuel and material tests in the Halden reactor,” in: 6th Int. Conf. on WWER Fuel Performance, Modelling and Experimental Support , Bulgaria, Albena, Sept. 19–23, 2005, pp. 214–221.

K. Vinjamuru and D. Owen, “Helium fill gas absorption in pressurized UO2 fuel rods during irradiation,” Nucl. Technol ., 47 , No. 1, 119–124 (1980).

G. Small, “Densification of uranium dioxide at low burnup,” J. Nucl. Mater. , 148 , No. 3, 302–315 (1987).

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M. Freshley et al., “Irradiation-induced densification of UO2 pellet fuel,” ibid ., 62 , No. 2, 138–166 (1976).

W. Wiesenack and T. Tverberg, “Thermal performance of high burnup fuel – in-pile temperature data and analysis,” in: Int. Topical Meeting on LWR Fuel Performance , Utah, USA, April 10–3, 2000, pp. 626–633.

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Halden Reactor Project, Halden, Norway

B. Yu. Volkov & W. Wiesenack

National Research Center Kurchatov Institute, Moscow, Russia

V. V. Yakovlev & E. P. Ryazantsev

Machine-Building Plant, Elektrostal, Moscow Oblast, Russia

A. K. Panyushkin, A. V. Ivanov & O. V. Kryukov

TVEL Company, Moscow, Russia

P. I. Lavrenyuk & Yu. V. Pimenov

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Translated from Atomnaya Énergiya, Vol. 113, No. 3, pp. 140–145, September, 2012.

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Volkov, B.Y., Wiesenack, W., Yakovlev, V.V. et al. Study of modified VVER and typical PWR fuel in the HBWR reactor (Norway). At Energy 113 , 171–178 (2013). https://doi.org/10.1007/s10512-012-9613-7

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Received : 14 February 2012

Published : 21 December 2012

Issue Date : January 2013

DOI : https://doi.org/10.1007/s10512-012-9613-7

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