Research on Manufacturing Technology of China Experimental Fast Reactor Fuel Rod

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.

2019 ◽  
Vol 34 (4) ◽  
pp. 313-324
Author(s):  
M. Khizer ◽  
Zhang Yong ◽  
Yang Guowei ◽  
Wu Qingsheng ◽  
Wu Yican

In this study, the structural integrity of liquid metal fast reactor fuel assembly has been established for different parameters considering the optimum fuel design. Analytical calculation of added mass effect due to lead bismuth eutectic and verification through previously presented theories, has been established. The integrity of the hexagonal wrapper of fuel assembly has been guaranteed over the entire operating temperature range. Effect of temperature on the density of lead bismuth eutectic, the subsequent change in added mass of lead bismuth eutectic, the effect on natural frequencies and effect on stresses on wrapper, has been studied in detail. A simple empirical relationship is presented for estimation of added mass effect for lead bismuth eutectic type fast reactors for any desired temperature. An approach for assessment of fast reactor fuel assembly performance has been outlined and calculated results are presented. Nuclear seismic rules require that systems and components which are important to safety, shall be capable of bearing earthquake effects and their integrity and functionality should be guaranteed. Mode shapes, natural frequencies, stresses on wrapper and seismic aspect has also been considered using ANSYS. Modal analysis has been compared in vacuum and lead bismuth eutectic using the calculated added mass.


2016 ◽  
Vol 298 ◽  
pp. 218-228 ◽  
Author(s):  
E. Merzari ◽  
P. Fischer ◽  
H. Yuan ◽  
K. Van Tichelen ◽  
S. Keijers ◽  
...  

1987 ◽  
Vol 62 (3) ◽  
pp. 183-189
Author(s):  
A. V. Zhukov ◽  
A. P. Sorokin ◽  
P. A. Ushakov ◽  
N. M. Matyukhin ◽  
P. A. Titov ◽  
...  

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.


1970 ◽  
Author(s):  
J.M. Yatabe ◽  
R.E. Collingham ◽  
V.R. Hill ◽  
T.I. McSweeney ◽  
W.L. Thorne

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