scholarly journals TWODIM: A COMPUTER CODE FOR UNFOLDING DIAMETRAL GAMMA-RAY SCANS ON REACTOR FUEL ELEMENTS.

1971 ◽  
Author(s):  
B.K. Barnes ◽  
J.R. Phillips
Keyword(s):  
Gamma Ray ◽  
Computer Code ◽  
Reactor Fuel ◽  
Fuel Elements

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.

Nondestructive Testing of Reactor Fuel Elements

1957 ◽  
Vol 2 (5) ◽  
pp. 602-616
Author(s):  
W. J. McGonnagle
Keyword(s):  
Nondestructive Testing ◽  
Reactor Fuel ◽  
Fuel Elements

scholarly journals Fabrication procedures for manufacturing High Flux Isotope Reactor fuel elements - 2

1999 ◽  
Author(s):  
R.W. Knight ◽  
R.A. Morin
Keyword(s):  
Reactor Fuel ◽  
High Flux ◽  
Fuel Elements

scholarly journals FABRICATION PROCEDURES FOR MANUFACTURING HIGH FLUX ISOTOPE REACTOR FUEL ELEMENTS.

1968 ◽  
Author(s):  
R.W. Knight ◽  
J. Binns ◽  
G.M. Jr. Adamson
Keyword(s):  
Reactor Fuel ◽  
High Flux ◽  
Fuel Elements

scholarly journals THE APPLICATION OF A NOMINAL 48 WT % U-Al ALLOY TO PLATE-TYPE ALUMINUM RESEARCH REACTOR FUEL ELEMENTS

1958 ◽  
Author(s):  
W C Thurber ◽  
J H Erwin ◽  
R J Beaver
Keyword(s):  
Research Reactor ◽  
Reactor Fuel ◽  
Al Alloy ◽  
Fuel Elements ◽  
Plate Type
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