scholarly journals Preparation of U–Zr–Mn, a Surrogate Alloy for Recycling Fast Reactor Fuel

2015 ◽  
Vol 2015 ◽  
pp. 1-8 ◽  
Author(s):  
Jong-Hwan Kim ◽  
Ki-Hwan Kim ◽  
Chan-Bock Lee

Metallic fuel slugs of U–10Zr–5Mn (wt%), a surrogate alloy for the U–TRU–Zr (TRU: a transuranic element) alloys proposed for sodium-cooled fast reactors, were prepared by injection casting in a laboratory-scale furnace, and their characteristics were evaluated. As-cast U–Zr–Mn fuel rods were generally sound, without cracks or thin sections. Approximately 68% of the original Mn content was lost under dynamic vacuum and the resulting slug was denser than those prepared under Ar pressure. The concentration of volatile Mn was as per the target composition along the entire length of the rods prepared under 400 and 600 Torr. Impurities, namely, oxygen, carbon, silicon, and nitrogen, totaled less than 2,000 ppm, satisfying fuel criteria.

2018 ◽  
Vol 15 (4) ◽  
pp. 991-998
Author(s):  
Ki-Hwan Kim ◽  
Ki-Won Hong ◽  
Jong-Hwan Kim ◽  
Jeong-Yong Park ◽  
Chan-Bock Lee

1979 ◽  
Vol 43 (1) ◽  
pp. 88-99 ◽  
Author(s):  
Helmut Elbel ◽  
José LóPez Jiménez

Author(s):  
Yu Hu ◽  
Jianhong Wang

CEFR, which is the acronym of China Experimental Fast Reactor, as the fourth generation advanced nuclear power system, plays a very important role in the development of nuclear industry in the future. Currently, as a kind of study, has not yet formed a fuel rod and fuel assembly manufacturing company in China. Realizing the localization of fast reactor fuel rod, fuel assembly and equipment has a very positive meaning to China’s nuclear industry development. At the same time for the CJNF’s development, promoting the manufacture level and scientific research technology of product, the research plays an extremely important role. In this paper, a fuel rod extrusion pit device and a fuel rod cladding pipe wire equipment have been designed according to the characteristic of fast reactor components. The fuel rod extrusion pit device to ensure pit deepness is 1.8–2.0mm, the radius of pit is 3mm, three pits into each other 120°, deviation is ±5°, the distance is 450.4±0.3mm. And the fuel rod cladding pipe wire equipment meet the product technical requirements for the pitch of 100±5mm, each distance deviation shall not be more than ±15mm, wire tension force for 100±20N. Massive tests on the extrude pits, press plug, load pellet, wire and spot welding, fuel rods ring welding and other important process step have been conducted and develop a set of optimized production plan. Fast reactor fuel rods structure have a enormous difference with the past other types of products have, the control of the input power for welding and an increase in the pressure of sealed welding chambers have been employed and avoided the problem of weld inflatable and weld porosity successfully. Results showed that the study on manufacturing of fast reactor fuel rod achieves success and realize the localization of fast reactor fuel rod in CJNF.


2009 ◽  
pp. 120-126
Author(s):  
K.V. Govindan Kutty ◽  
P.R. Vasudeva Rao ◽  
Baldev Raj

2018 ◽  
Author(s):  
G Padmakumar ◽  
K. Velusamy ◽  
Bhamidi V. S. S. S. Prasad ◽  
P Lijukrishnan ◽  
P. Selvaraj

1965 ◽  
Vol 1 (1) ◽  
pp. 55-61 ◽  
Author(s):  
F. R. Channon ◽  
J. D. Luoma ◽  
E. D. Frankhouser

2013 ◽  
Vol 39 ◽  
pp. 43-51
Author(s):  
Kyoko Mukaida ◽  
Hiroki Shiotani ◽  
Kiyoshi Ono ◽  
Takashi Namba

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