Download or read book Fission Gas Release from Fuel at High Burnup written by Ralph O. Meyer and published by . This book was released on 1978 with total page 78 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission Gas Release from High Burnup ThO sub 2 and ThO sub 2 UO sub 2 Fuels Irradiated at Low Temperature LWBR AWBA Development Program LWBR Below 2700 sup 0 F written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission gas release data are presented for five fuel rods irradiated at low fuel temperature (below 2700/sup 0/F) with burnups up to 90,000 MWD/MTM. Four of these rods contained ThO/sub 2/-UO/sub 2/ (33.6 weight percent UO/sub 2/) fuel pellets; the fifth rod contained ThO/sub 2/ pellets. These data supplement fission gas release information previously reported for 54 rods containing ThO/sub 2/-UO/sub 2/ and ThO/sub 2/ fuel, some of which experienced fuel temperaures up to 5000/sup 0/F and burnups to 56,000 MWD/MTM. These new data suggest that at burnups exceeding about 80,000 MWD/MTM a sharp increase in fission gas release occurs, possibly caused by microstructural changes in the fuel. This is similar to the behavior of UO/sub 2/ except that the increase occurs in UO/sub 2/ at lower burnup (approximately 40,000 MWD/MTM). The fission gas release calculational model previously reported has been modified to account for the observed increase in the low temperature component. The revised model provides a good best estimate of all the fission gas release data.

Download or read book Prediction of Fission Gas Release from High Burnup Oxide Fuel written by and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Prediction of Fission Gas Release from High Burnup Oxide Fuel written by Atomic Energy of Canada Limited and published by Chalk River, Ont. : Chalk River Nuclear Laboratories. This book was released on 1979 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission gas Release from Uranium Nitride at High Fission rate Density written by Michael B. Weinstein and published by . This book was released on 1973 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt: A sweep gas facility has been used to measure the release rates of radioactive fission gases from small UN specimens irradiated to 8-percent burnup at high fission-rate densities. The measured release rates have been correlated with an equation whose terms correspond to direct recoil release, fission-enhanced diffusion, and atomic diffusion (a function of temperature). Release rates were found to increase linearly with burnups between 1.5 and 8 percent. Pore migration was observed after operation at 1550 K to over 6 percent burnup.

Download or read book The Behavior of Fission Gas in Fuels written by and published by . This book was released on 1965 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission Gas Behaviour in Water Reactor Fuels written by and published by Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development. This book was released on 2002 with total page 572 pages. Available in PDF, EPUB and Kindle. Book excerpt: Communicates the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors.

Download or read book Fission Gases Their Measurement and Evaluation written by T. J. Slosek and published by . This book was released on 1960 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book In pile Fission gas release Behavior of Alumina coated UO2 Particles Irradiated to High Burnup written by Gilbert E. Raines and published by . This book was released on 1961 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission Gas Release from Oxide Fuels at High Burnups AWBA Development Program written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The steady state gas release, swelling and densification model previously developed for oxide fuels has been modified to accommodate the slow transients in temperature, temperature gradient, fission rate and pressure that are encountered in normal reactor operation. The gas release predictions made by the model were then compared to gas release data on LMFBR-EBRII fuels obtained by Dutt and Baker and reported by Meyer, Beyer, and Voglewede. Good agreement between the model and the data was found. A comparison between the model and three other sets of gas release data is also shown, again with good agreement.

Download or read book Modelling of Fission Gas Behaviour in High Burnup Nuclear Fuel written by Paul Blair and published by . This book was released on 2008 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation and Examination of Vibratory Packed UO2 High Burnup Program Fuel Elements written by T. J. Slosek and published by . This book was released on 1960 with total page 78 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Analysis of UO 2 Fuel Structure for Low and High Burn up and Its Impact on Fission Gas Release written by Marcin Szuta and published by . This book was released on 1999 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission Gas Induced Fuel Swelling in Low and Medium Burnup Fuel During High Temperature Transients PWR written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The behavior of light water reactor fuel elements under postulated accident conditions is being studied by the EG and G Idaho, Inc., Thermal Fuels Behavior Program for the Nuclear Regulatory Commission. As a part of this program, unirradiated and previously irradiated, pressurized-water-reactor type fuel rods were tested under power-cooling-mismatch (PCM) conditions in the Power Burst Facility (PBF). During these integral in-reactor experiments, film boiling was produced on the fuel rods which created high fuel and cladding temperatures. Fuel rod diameters increased in the film boiling region to a greater extent for irradiated rods than for unirradiated rods. The purpose of the study was to investigate and assess the fuel swelling which caused the fuel rod diameter increases and to evaluate the ability of an analytical code, the Gas Release and Swelling Subroutine - Steady-State and Transient (GRASS-SST), to predict the results.

Download or read book Models for Fission gas Release from Coated Fuel Particles written by John W. Prados and published by . This book was released on 1963 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Uranium Dioxide written by J. Belle and published by . This book was released on 1961 with total page 744 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission Gas Release from ThO2 and ThO2 UO2 Fuels LWBR Development Program written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission gas release data are presented from 51 fuel rods irradiated as part of the LWBR irradiations test program. The fuel rods were Zircaloy-4 clad and contained ThO2 or ThO2-UO2 fuel pellets, with UO2 compositions ranging from 2.0 to 24.7 weight percent and fuel densities ranging from 77.8 to 98.7 percent of theoretical. Rod diameters ranged from 0.25 to 0.71 inches and fuel active lengths ranged from 3 to 84 inches. Peak linear power outputs ranged from 2 to 22 kw/ft for peak fuel burnups up to 56,000 MWD/MTM. Measured fission gas release was quite low, ranging from 0.1 to 5.2 percent. Fission gas release was higher at higher temperature and burnup and was lower at higher initial fuel density. No sensitivity to UO2 composition was evidenced.