scholarly journals LMFBR source term iodine attenuation test of bubble breakup/coalescence in LMFBR outlet plenum following large fission gas release

1975 ◽  
Author(s):  
D Dickinson ◽  
F Nunamaker
Keyword(s):  
Source Term ◽  
Gas Release ◽  
Bubble Breakup ◽  
Fission Gas ◽  
Fission Gas Release

Measurements of Grain-Boundary Inventories of 137Cs, 90Sr and 99Tc in Used Candu Fuel

1992 ◽  
Vol 294 ◽  
Author(s):  
S. Stroes-Gascoyne ◽  
J.C. Tait ◽  
R.J. Porth ◽  
J.L. Mcconnell ◽  
T.R. Barnsdale ◽  
...  
Keyword(s):  
Aqueous Solution ◽  
Grain Boundary ◽  
Grain Boundaries ◽  
Source Term ◽  
Slow Release ◽  
Gas Release ◽  
System A ◽  
Fission Gas ◽  
Fission Gas Release ◽  
Upper Boundary

ABSTRACTTwo methods were used to measure grain-boundary inventories of 137Cs, 90Sr and 99Tc in used CANDU fuel, to corroborate source term estimates based on a fission gas release code. Used fuels were partially oxidized at 200°C in air to overall compositions of UO2+x (0.15≤ × ≤0.25) to expose UO2 grain boundaries, followed by leaching in aqueous solution. Only a fraction (2 to 18%) of the calculated gap + grain-boundary inventories for 37Cs was released. This suggests that the calculations overestimate Cs release or that oxidation does not expose all grain boundaries, or that Cs release from grain boundaries is slow. Release of 90Sr (0.01 to 0.7%) agreed reasonably well with the source term estimates (0.001 to 0.3%). Release of 99Tc (0.3 to 1.5%) suggests that the source term estimate for the upper boundary of 99Tc release (25%) may be too high. A second technique involved leaching of crushed and size-fractionated used fuel in either a static or dynamic system. A direct one-to-one correlation between calculated and measured gap + grain-boundary inventories for 137Cs was found for low- and medium-power fuels.

Fission Gas Release from Irradiated Uranium-Plutonium Nitride Fuel

Atomic Energy ◽  
2020 ◽  
Vol 129 (2) ◽  
pp. 103-107
Author(s):  
A. F. Grachev ◽  
L. M. Zabud’ko ◽  
M. V. Skupov ◽  
F. N. Kryukov ◽  
V. G. Teplov ◽  
...  
Keyword(s):  
Gas Release ◽  
Nitride Fuel ◽  
Fission Gas ◽  
Uranium Plutonium ◽  
Fission Gas Release

Fission gas release and swelling in uranium–plutonium mixed nitride fuels

2004 ◽  
Vol 327 (2-3) ◽  
pp. 77-87 ◽  
Author(s):  
Kosuke Tanaka ◽  
Koji Maeda ◽  
Kozo Katsuyama ◽  
Masaki Inoue ◽  
Takashi Iwai ◽  
...  
Keyword(s):  
Gas Release ◽  
Fission Gas ◽  
Nitride Fuels ◽  
Uranium Plutonium ◽  
Fission Gas Release

Pellet-Cladding Interaction of LMFBR Fuel Elements at Unsteady State: An Introduction to Computer Code ISUNE-5

1981 ◽  
Vol 103 (4) ◽  
pp. 627-636 ◽  
Author(s):  
B. M. Ma
Keyword(s):  
Reactor Core ◽  
Fatigue Cracking ◽  
Computer Code ◽  
Fuel Burnup ◽  
Fuel Pellet ◽  
Gas Release ◽  
Unsteady State ◽  
Fission Gas ◽  
Fuel Elements ◽  
Fission Gas Release

The fuel pellet-cladding interaction (PCI) of liquid-metal fast breeder reactor (LMFBR) fuel elements or fuel rods at unsteady state is analyzed and discussed based on experimental results. In the analyses, the heat generation, fuel restructuring, temperature distribution, gap conductance, irradiation swelling, irradiation creep, fuel burnup, fission gas release, fuel pellet cracking, crack healing, cladding cracking, yield failure and fracture failure of the fuel elements are taken into consideration. To improve the sintered (U,Pu)O2 fuel performance and reactor core safety at high temperature and fuel burnup, it is desirable to (a) increase and maintain the ductility of cladding material, (b) provide sufficient gap thickness and plenum space for accommodating fission gas release, (c) keep ramps-power increase rate slow and gentle, and (d) reduce the intensity and frequency of transient PCI in order to avoid intense stress fatigue cracking (SFC) and stress corrosion cracking (SCC) due to fission product compounds CsI, CdI2, Cs2Te, etc. at the inner cladding surface of the fuel elements during PCI.

The role of bubbles in fission gas release from uranium dioxide

1969 ◽  
Vol 30 (1-2) ◽  
pp. 170-178 ◽  
Author(s):  
R.M. Cornell ◽  
M.V. Speight ◽  
B.C. Masters
Keyword(s):  
Uranium Dioxide ◽  
Gas Release ◽  
Fission Gas ◽  
Fission Gas Release

Measurement of fission gas release from irradiated U–Mo monolithic fuel samples

2015 ◽  
Vol 461 ◽  
pp. 61-71 ◽  
Author(s):  
Douglas E. Burkes ◽  
Amanda J. Casella ◽  
Andrew M. Casella ◽  
Walter G. Luscher ◽  
Francine J. Rice ◽  
...  
Keyword(s):  
Gas Release ◽  
Fission Gas ◽  
Fission Gas Release
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