scholarly journals POST IRRADIATION EXAMINATION OF THORIA--URANIA FUEL RODS. Quarterly Progress Report No. 1, March--August 1967.

1968 ◽  
Author(s):  
W. N. Bishop ◽  
S. F. Marsh ◽  
C. J. Baroch
Keyword(s):  
Progress Report ◽  
Fuel Rods ◽  
Post Irradiation

scholarly journals POST-IRRADIATION ANALYSES OF U-MO DISPERSION FUEL RODS OF KOMO TESTS AT HANARO

2013 ◽  
Vol 45 (7) ◽  
pp. 847-858 ◽  
Author(s):  
H.J. RYU ◽  
J.M. PARK ◽  
Y.J. JEONG ◽  
K.H. LEE ◽  
Y.S. LEE ◽  
...  
Keyword(s):  
Fuel Rods ◽  
Dispersion Fuel ◽  
Post Irradiation

Test Reactor Irradiation Fuel Assembly Development in China

2017 ◽  
Author(s):  
Jie Ding ◽  
Yixiong Zheng ◽  
Yang Ding ◽  
Song Liu ◽  
Libing Zhu ◽  
...  
Keyword(s):  
Fuel Assembly ◽  
Zirconium Alloys ◽  
Reactor Irradiation ◽  
Fuel Rods ◽  
Post Irradiation ◽  
Irradiation Growth ◽  
Corrosion Creep ◽  
Test Reactor ◽  
Irradiation Performance ◽  
Test Fuel

During the development of zirconium alloys, the irradiation in the test reactor is a critical step to comparison the irradiation properties of candidate alloys, such as corrosion, creep and irradiation growth. In this paper, a small scaled fuel assembly for test reactor irradiation is designed, which meets the needs of new zirconium alloys development. The irradiation fuel assembly (IFA) can be easily disassembled, and the test fuel rods or irradiation specimen can be easily replaced, which makes it possible to do the further post-irradiation examination in the hot cell to obtain the irradiation performance data. Now the IFA has finish fabrication and the test reactor irradiation program is planned to launch in 2017.

Post-irradiation examinations of dispersion fuel rods with modified zirconium alloys claddings

2019 ◽  
pp. 206-212
Author(s):  
G. V. Kulakov ◽  
Y. V. Konovalov ◽  
A. A. Kosaurov ◽  
M. M. Peregud ◽  
V. Y. Shishin ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Corrosion Resistance ◽  
Master Alloy ◽  
Zirconium Alloys ◽  
High Strength ◽  
Fuel Rods ◽  
Dispersion Fuel ◽  
Post Irradiation ◽  
Strength And Ductility

Modified zirconium alloys E635Mand E635opt based on E635 alloy (E635 was selected as master alloy) have been developed at Bochvar Institute. Fuel rods with such claddings were manufactured at Bochvar Institute and were irradiated at MIR reactor (SC RIAR, Dimitrovgrad). The results from the PIE performed at RIAR are presented. Such features of claddings as microstructures, corrosion resistance (width and structure of oxide), hydrogen contents, distribution of hydrides, mechanical properties were examined and discussed. Modifications of the alloy E635opt and E635M showed higher resistance to corrosion and hydrogen pick-up compared to the E635 alloy, while maintaining high strength and ductility. They have confirmed their prospects for use as cladding for fuel rods with enhanced characteristics.

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