Design Study on a Fast Reactor Metal Fuel Attaining Very High Burnup

2014 ◽  
Vol 187 (2) ◽  
pp. 198-207 ◽  
Author(s):  
Hirokazu Ohta ◽  
Takanari Ogata ◽  
Toru Obara
Keyword(s):  
Fast Reactor ◽  
Design Study ◽  
Metal Fuel ◽  
High Burnup ◽  
Very High

scholarly journals Conceptual Core Design Study of the Very High Temperature Gas-Cooled Reactor (VHTR) Upgrading the Core Performance by Using Multihole-Type Fuel

2008 ◽  
Vol 7 (1) ◽  
pp. 32-43 ◽  
Author(s):  
Kazutaka OHASHI ◽  
Tetsuo NISHIHARA ◽  
Kazuhiko KUNITOMI ◽  
Masaaki NAKANO ◽  
Yujiro TAZAWA ◽  
...  
Keyword(s):  
High Temperature ◽  
Design Study ◽  
The Core ◽  
Conceptual Core ◽  
Very High ◽  
Type Fuel ◽  
High Temperature Gas

A design study of atmospheric Cerenkov radiation telescope for very high energy gamma-ray astronomy

1985 ◽  
Vol 115 (1) ◽  
pp. 163-183 ◽  
Author(s):  
S. K. Gupta ◽  
P. V. Ramana Murthy ◽  
S. C. Tonwar ◽  
P. R. Vishwanath
Keyword(s):  
Gamma Ray ◽  
High Energy ◽  
Cerenkov Radiation ◽  
Design Study ◽  
Gamma Ray Astronomy ◽  
High Energy Gamma ◽  
Very High Energy ◽  
Energy Gamma ◽  
Very High

HT9 swelling in high burnup fast reactor fuel pin components

2019 ◽  
Vol 519 ◽  
pp. 205-216 ◽  
Author(s):  
D.L. Porter ◽  
B.D. Miller ◽  
B.A. Hilton ◽  
M.M. Jones
Keyword(s):  
Fast Reactor ◽  
Reactor Fuel ◽  
Fuel Pin ◽  
Fast Reactor Fuel ◽  
High Burnup

TEM characterization of high burnup fast-reactor MOX fuel

2019 ◽  
Vol 527 ◽  
pp. 151794 ◽  
Author(s):  
Riley Parrish ◽  
Alexander Winston ◽  
Jason Harp ◽  
Assel Aitkaliyeva
Keyword(s):  
Fast Reactor ◽  
Tem Characterization ◽  
Mox Fuel ◽  
High Burnup

scholarly journals A Design Study on the FBR Metal Fuel and Core for Commercial Applications

2000 ◽  
Vol 37 (8) ◽  
pp. 636-645 ◽  
Author(s):  
Takeshi YOKOO ◽  
Takanari OGATA ◽  
Hirokazu OHTA
Keyword(s):  
Design Study ◽  
Metal Fuel ◽  
Commercial Applications

Concluding remarks

1990 ◽  
Vol 331 (1619) ◽  
pp. 451-453
Keyword(s):  
Soviet Union ◽  
Technical Progress ◽  
Fast Reactor ◽  
Mixed Oxide ◽  
Electrical Power ◽  
The Past ◽  
The Soviet Union ◽  
Fuel Storage ◽  
Metal Fuel ◽  
Versus Loop

Over the past two days we have been taking stock of the overall position as regards the development of fast reactors in Europe, the U. S. S. R., the U. S. A, and Japan. I am sure we can agree that collectively we have made good technical progress with the development of this major source of electrical power for the next century. In Europe, we have two large prototypes operating, Phénix and PER. We also have a 1200 MW e demonstration reactor (Superphenix), which is now continuing with its commissioning programme after the interruption caused by the leak from the fuel storage vessel. The Soviet Union is pressing ahead with its program m e; in the U. S. A. FFTF has given outstanding reliability and in Jap an the construction of Monju is going well and is on schedule for criticality in 1992. O f course there are a number of possible realizations of the sodium-cooled fast reactor concept. We have had in this conference some muted debates about the merits of pool versus loop, oxide versus metal fuel, large versus small modular and the possibilities of eliminating the secondary sodium circuit. But we can all probably agree that the pool mixed-oxide fuelled design is one realization which has now reached an advanced state of development, certainly the pre-commercial stage.

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