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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 through the risky ones similar to krypton and xenon, known as fission fuel. Fission fuel behaviour should be reliably envisioned so that it will make higher use of nuclear gasoline, an element that could aid to accomplish the commercial competitiveness required by way of present day markets. those complaints speak the result of a world seminar which reviewed fresh development within the box of fission gasoline behaviour in gentle water reactor gas and sought to enhance the versions utilized in computing device codes predicting fission gasoline liberate. cutting-edge wisdom is gifted for either uranium-oxide and mixed-oxide fuels loaded in water reactors.
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Extra resources for Fission Gas Behaviour in Water Reactor Fuels: Seminar Proceedings, Cadarache, France, 26-29 September 2000
The authors also gratefully acknowledge MITI for acceptance of this report. 52 REFERENCES  H. , “Irradiation Characteristics of High Burn-up BWR Fuels”, Int. Topical Mtg. on LWR Fuel Performance, Park City, Utah, 9-13 April 2000.  K. , “Microstructural Change and its Influence on Fission Gas Release in High Burn-up UO2 Fuel”, J. Nucl. , 188, 65, 1992. E. , J. Nucl. , 188, 19, 1972.  R. , “The Role of the Pellet Rim on Fission Gas Release at Extended Burn-up”, IAEA Technical Committee Meeting on Advances in Pellet Technology for Improved Performance at High Burn-up, Tokyo, Japan, 29 October-1 November 1996.
Results and discussion Fission gas release Along with published BWR data , the FGR fraction of Step II LUAs is shown in Figure 2 (as a function of rod average burn-up) and Figure 3 (related to the maximum power experienced at burn-up beyond 10 GWd/t). Except for two fuel rods which experienced relatively high power among Step II LUAs, the FGR fraction of Step II LUAs was up to about 5% throughout the irradiation cycles. When compared at the same power experienced during irradiation, the FGR fraction of Step II LUAs was less than that of the previous types of fuel rods, indicating effectiveness of the design improvements to reduce FGR.
0 0 0 10 20 30 40 50 Rod average burn-up, MWd/kg U 32 60 Fractional fission gas release % Figure 2. Fractional fission gas release as a function of rod average burn-up  30 25 20 15 10 5 0 0 20 40 60 80 100 Rod average burn-up MWd/kg U • Achievement at moderate temperature (<1 000°C) of local burn-up above 50 GWd/tM (typically) leads to the so-called “rim structure”. This is the object of extensive studies concerning its formation mechanism and its impact on thermal conductivity and local FGR.
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