Download PDF by OECD - Organisation for Economic Co-operation and: Pellet-Clad Interaction in Water Reactor Fuels: Seminar

By OECD - Organisation for Economic Co-operation and Development

ISBN-10: 9264011579

ISBN-13: 9789264011571

ISBN-10: 9264011587

ISBN-13: 9789264011588

This file communicates the result of a world seminar which reviewed fresh growth within the box of pellet-clad interplay in gentle water reactor fuels. It additionally attracts a entire photograph of present knowing of appropriate phenomena and their impression at the nuclear gasoline rod, lower than the widest attainable stipulations. cutting-edge wisdom is gifted for either uranium-oxide and mixed-oxide fuels.

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Read Online or Download Pellet-Clad Interaction in Water Reactor Fuels: Seminar Proceedings, Aix-en-Provence, France, 9-11 March 2004 PDF

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Additional info for Pellet-Clad Interaction in Water Reactor Fuels: Seminar Proceedings, Aix-en-Provence, France, 9-11 March 2004

Sample text

Development of Zirconium-barrier Fuel Cladding”, 10th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1245, pp. 3-18 (1994). , “Overview of EPRI Fuel Performance Code FALCON”, OECD/NEA Proceedings of Meeting on Thermal Performance of High Burn-up LWR Fuel, Cadarache, 3-6 March 1998. L. R. O. Montgomery, R. , “Modeling of Fuel Rod Steady State and Transient Behavior over the Full Range of Burn-up”, Transactions of the ANS Winter Meeting, Albuquerque, NM, November 1997. [7] Power Ramp Testing of Additive Fuel Rods in the Halden Reactor, EPRI, Palo Alto, CA, 1002855 (2003).

A threshold stress, Vref, and a minimum burn-up (>5 GWd/tU) are used in the model and both of these values must be exceeded before SCC is initiated. As shown, the threshold stress decreases as function of burn-up and reaches a minimum value near 25 ksi above 20 GWd/tU. The damage index is calculated in FALCON at each clad element to indicate the potential for cladding failure as a function of time and stress level. The damage index is given by: tn D dt ³ t V, Bu, T 0 (3) f where D is the amount of damage at tn, tf is the failure time at stress V, temperature T and burn-up Bu.

R. O. Montgomery, R. , “Modeling of Fuel Rod Steady State and Transient Behavior over the Full Range of Burn-up”, Transactions of the ANS Winter Meeting, Albuquerque, NM, November 1997. [7] Power Ramp Testing of Additive Fuel Rods in the Halden Reactor, EPRI, Palo Alto, CA, 1002855 (2003). , “Performance of Advanced Fuel Materials for High Burn-up”, Proceedings of the ENS TopFuel 2003 Conference, Würzburg, March 2003. , “The International OVER-RAMP Project at Studsvik”, Proceedings of ANS Topical Meeting on Fuel Performance, Williamsburg, VA, USA, April 1982.

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Pellet-Clad Interaction in Water Reactor Fuels: Seminar Proceedings, Aix-en-Provence, France, 9-11 March 2004 by OECD - Organisation for Economic Co-operation and Development


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