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In the course of irradiation, nuclear gasoline alterations quantity, essentially via swelling. This swelling is as a result of the fission items and specifically by way of the unstable ones corresponding to krypton and xenon, referred to as fission gasoline. Fission gasoline behaviour should be reliably anticipated so as to make greater use of nuclear gas, an element which could aid to accomplish the industrial competitiveness required through state-of-the-art markets. those lawsuits converse the result of a global seminar which reviewed fresh growth within the box of fission fuel behaviour in mild water reactor gas and sought to enhance the versions utilized in machine codes predicting fission fuel unlock. cutting-edge wisdom is gifted for either uranium-oxide and mixed-oxide fuels loaded in water reactors.

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Extra info for Fission Gas Behaviour in Water Reactor Fuels: Seminar Proceedings, Cadarache, France, 26-29 September 2000

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Smirnov, B. Kanashov, S. Kuzmin, F. Kryukov, I. Kungurtzev, G. Lyadov RIAR A. Panyushkin, Eu. Bek JSC “MSZ” Abstract Fission gas release (FGR) from VVER-440 fuel under steady-state and transient operation conditions is an essential parameter determining fuel rod efficiency. The importance of fission gas release increases as burn-up increases. ), dimensions and thermal conductivity of fuel-cladding gap, more “feedbacks” appear, which accelerate fission gas release. It was established that intensification of FGR occurs at fuel temperatures above 1 050-1 100°C and linear power at these temperatures decreased along with burn-up.

264, 99-112, 1999. 43 [5] M. Verwerft, “Multiple Voltage Electron Probe Microanalysis of Fission Gas Bubbles in Irradiated Nuclear Fuel”, accepted for publication in Journal of Nuclear Materials. [6] N. , “Experience and Development of BWR Fuel Supplied by NFI”, International Topical Meeting on Light Water Reactor Fuel Performance, Park City, Utah, April 2000. [7] R. Manzel, R. Eberle, “Fission Gas Release at High Burn-up and the Influence of Pellet Rim”, International Topical Meeting on LWR Fuel Performance, Avignon, France, April 1991.

2. Additional FGR during power ramp tests depended strongly on RTP, burn-up and cumulative holding time. 3. FGR was mainly due to the release of fission gas retained at the grain boundaries through the growth and interlinkage of grain boundary bubbles and formation of grain edge tunnels. 4. Cs migration may be disturbed under higher power and strong PCI restriction. Acknowledgements This study was carried out mainly under the direction of committees of NUPEC. The authors wish to express their gratitude to the members of the Committee of Verification Tests on High Burn-up Fuel for their discussions and evaluations with respect to this programme.

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