Fission Gas Release from Fuel at High Burnup
Author : Ralph O. Meyer
Publisher :
Page : 78 pages
File Size : 36,18 MB
Release : 1978
Category : Fission gases
ISBN :
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].
Author :
Publisher :
Page : pages
File Size : 13,75 MB
Release : 1982
Category :
ISBN :
Book Description
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.
Prediction of Fission Gas Release from High Burnup Oxide Fuel
Author :
Publisher :
Page : 0 pages
File Size : 29,85 MB
Release : 1980
Category :
ISBN :
Book Description
Prediction of Fission Gas Release from High Burnup Oxide Fuel
Author : Atomic Energy of Canada Limited
Publisher : Chalk River, Ont. : Chalk River Nuclear Laboratories
Page : 11 pages
File Size : 44,63 MB
Release : 1979
Category :
ISBN :
Book Description
Fission-gas Release from Uranium Nitride at High Fission-rate Density
Author : Michael B. Weinstein
Publisher :
Page : 68 pages
File Size : 37,60 MB
Release : 1973
Category : Fission gases
ISBN :
Book Description
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.
Fission Gases, Their Measurement and Evaluation
Author : T. J. Slosek
Publisher :
Page : 24 pages
File Size : 14,46 MB
Release : 1960
Category : Fission gases
ISBN :
Book Description
Fission Gas Release from Oxide Fuels at High Burnups (AWBA Development Program).
Author :
Publisher :
Page : pages
File Size : 45,86 MB
Release : 1981
Category :
ISBN :
Book Description
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.
Irradiation and Examination of Vibratory Packed UO2 High Burnup Program Fuel Elements
Author : T. J. Slosek
Publisher :
Page : 78 pages
File Size : 42,44 MB
Release : 1960
Category : Fuel burnup (Nuclear engineering)
ISBN :
Book Description
Fission Gas Induced Fuel Swelling in Low and Medium Burnup Fuel During High Temperature Transients. [PWR].
Author :
Publisher :
Page : pages
File Size : 47,67 MB
Release : 1980
Category :
ISBN :
Book Description
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.
Fission Gas Release from ThO2 and ThO2--UO2 Fuels (LWBR Development Program).
Author :
Publisher :
Page : pages
File Size : 11,18 MB
Release : 1978
Category :
ISBN :
Book Description
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.
