cermet fuel
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Corrigendum to “U-PuO2, U-PuC, U-PuN cermet fuel for fast reactor” [J. Nucl. Mater. 499 (2018) 272–283]

2018 ◽  
Vol 512 ◽  
pp. 482
Author(s):  
Sudhir Mishra ◽  
Santu Kaity ◽  
Joydipta Banerjee ◽  
Chiranjeet Nandi ◽  
G.K. Dey ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Cermet Fuel

Corrigendum to “Compatibility study between U-UO2 cermet fuel and T91 cladding” [J. Nucl. Mater. 481 (2016) 1–12]

2018 ◽  
Vol 512 ◽  
pp. 481
Author(s):  
Sudhir Mishra ◽  
Santu Kaity ◽  
K.B. Khan ◽  
Pranesh Sengupta ◽  
G.K. Dey
Keyword(s):  
Compatibility Study ◽  
Cermet Fuel

Corrigendum to “Cermet fuel for fast reactor – Fabrication and characterization” [J.Nucl. Mater. 442 (2013) 400–407]

2018 ◽  
Vol 512 ◽  
pp. 480
Author(s):  
Sudhir Mishra ◽  
P.S. Kutty ◽  
T.R.G. Kutty ◽  
Shantanu Das ◽  
G.K. Dey ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Cermet Fuel ◽  
Fabrication And Characterization

Thermionic Fuel Element with Cermet Fuel

Atomic Energy ◽  
2018 ◽  
Vol 124 (6) ◽  
pp. 392-397
Author(s):  
A. S. Gontar’ ◽  
M. V. Nelidov ◽  
V. N. Sotnikov
Keyword(s):  
Fuel Element ◽  
Cermet Fuel

In situ transmission electron microscopic observations of redox cycling of a Ni–ScSZ cermet fuel cell anode

Microscopy ◽  
2018 ◽  
Vol 67 (5) ◽  
pp. 251-258 ◽  
Author(s):  
Junko Matsuda ◽  
Tatsuya Kawasaki ◽  
Shotaro Futamura ◽  
Tsutomu Kawabata ◽  
Shunsuke Taniguchi ◽  
...  
Keyword(s):  
Fuel Cell ◽  
Redox Cycling ◽  
Electron Microscopic ◽  
Transmission Electron ◽  
Transmission Electron Microscopic ◽  
Cermet Fuel ◽  
Cell Anode ◽  
Fuel Cell Anode

U-PuO2, U-PuC, U-PuN cermet fuel for fast reactor

2018 ◽  
Vol 499 ◽  
pp. 272-283 ◽  
Author(s):  
Sudhir Mishra ◽  
Santu Kaity ◽  
Joydipta Banerjee ◽  
Chiranjeet Nandi ◽  
G.K. Dey ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Cermet Fuel

Compatibility study between U-UO2 cermet fuel and T91 cladding

2016 ◽  
Vol 481 ◽  
pp. 1-12 ◽  
Author(s):  
Sudhir Mishra ◽  
Santu Kaity ◽  
K.B. Khan ◽  
Pranesh Sengupta ◽  
G.K. Dey
Keyword(s):  
Compatibility Study ◽  
Cermet Fuel

Neutronics and thermal hydraulics analysis of a low-enriched uranium cermet fuel core for a Mars surface power reactor

2016 ◽  
Vol 96 ◽  
pp. 307-312 ◽  
Author(s):  
Kevin J. Schillo ◽  
Akansha Kumar ◽  
Kurt E. Harris ◽  
Yayu M. Hew ◽  
Steven D. Howe
Keyword(s):  
Power Reactor ◽  
Thermal Hydraulics ◽  
Cermet Fuel ◽  
Enriched Uranium
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