Determination of the rod-wise fission gas release fraction in a complete fuel assembly using non-destructive gamma emission tomography

2016 ◽  
Vol 837 ◽  
pp. 99-108 ◽  
Author(s):  
Scott Holcombe ◽  
Peter Andersson ◽  
Staffan Jacobsson Svärd ◽  
Lars Hallstadius
Keyword(s):  
Fuel Assembly ◽  
Emission Tomography ◽  
Gas Release ◽  
Gamma Emission ◽  
Fission Gas ◽  
Non Destructive ◽  
Fission Gas Release

Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions

2016 ◽  
Vol 479 ◽  
pp. 67-75 ◽  
Author(s):  
E. González-Robles ◽  
V. Metz ◽  
D.H. Wegen ◽  
M. Herm ◽  
D. Papaioannou ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Gas Release ◽  
Anoxic Conditions ◽  
Fission Gas ◽  
Leaching Experiments ◽  
Fission Gas Release

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

scholarly journals Fission Gas Release from Uranium Heated in Carbon Dioxide

1965 ◽  
Vol 2 (5) ◽  
pp. 168-171
Author(s):  
Kiyoaki TAKETANI ◽  
Katsuichi IKAWA
Keyword(s):  
Carbon Dioxide ◽  
Gas Release ◽  
Fission Gas ◽  
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
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