journal article·2021-01Open access

Fabrication of fuel element core (FEC) of U–6Zr–5Nb/Al to be fuel element plate (FEP) with variation of uranium density

Masrukan Masrukan, M.H. Al Hasa, E. Yusnitha

Abstract

Fabrication of fuel element core (FEC) of U–6Zr–5Nb/Al to be fuel element plate (FEP) with variation of uranium density has been conducted. The purpose of this study is to obtain the process parameters of fabrication FEP of U–6Zr–5Nb/Al. The composition of 89 wt.%U, 6 wt.%Zr, and 5 wt.%Nb metals were melted using an electric arc melting furnace to obtain U–6Zr–5Nb ingot, which was then processed by hydriding-dehydriding process to be U–6Zr–5Nb powder. The U–6Zr–5Nb powder was added with Al powder with weight ratio according to uranium meat density of 5.2, 6.0 and 7.0 gU/cm3. The mixture of U–6Zr–5Nb powder was pressed and put into the frame and closed with AlMg2 plate and rolled through four stages rolling process at temperature of 425 °C and continued with cold rolling to obtain a FEP with thickness of 1.47 mm. The FEP was partially cut for metallographic testing purpose by observing the condition of the meat and the thickness of the cladding. Others plates were analyzed to observe the white spots and blisters. The testing results show that the thickness cladding for FEP of U–6Zr–5Nb/Al with U density of 5.2 and 6.0 gU/cm3 has met the requirements. No white spots and blisters were found in all examined FEP of U–6Zr–5Nb/Al with U density of 5.2, 6.0 and 7.0 gU/cm3. Overall, the experiment process of making FEP of U–6Zr–5Nb/Al has met the specified requirements.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear and radioactivity studies

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References (19)

Show source-provided references
1. Manufacturing and characterization of U-Zr alloys for PWR reactor
2. Correlation of elemental composition with thermal properties of U-Zr-Hx fuel
3. Powder Production of uranium molybdenum-metal alloys applying hydride-dehydride methodology
4. Development of U-Mo-based uranium alloys as nuclear fuel candidates for research reactors replacing U3Si2-Al dispersion fuels
5. Metal fuel development and verification for prototype generation IV Sodium-Cooled Fast Reactor10.1016/j.net.2016.08.001 ↗
6. Moore · 2016
7. Fabrication of U-10 wt.%Zr metallic fuel rodlets for irradiation test in BOR -60 fast reactor
8. Density functional study of U-Mo and U-Zr alloys
9. Study of the change process as fuel U-Mo powder dispersion U-Mo/Al for a research reactor
10. Effect of Nb element content U-Zr alloy on hardness, microstructure and phase formation
11. Basak · 2011 · 1
12. National progress report on R&D on leu fuel and target technology in Argentina
13. Methodology of U-Zr-Nb alloy powder passivation obtained by hydride-dehydride process
14. Technical ability of new MTR high density fuel alloys regarding the whole fuel cycle
15. Transformation behavior of the γU(Zr,Nb) phase under continuous cooling conditions10.1016/j.jnucmat.2014.06.044 ↗
16. Synthesis and structural characterization of U-Zr-Nb alloys10.1590/1980-5373-mr-2017-0411 ↗
17. First results of scanning thermal diffusivity microscope (STDM) measurements on irradiated monolithic and disperse fuel
18. Irradiation performance of U-Mo monolithic fuel10.5516/NET.07.2014.706 ↗
19. Blister defect analysis of materials fuel U3Si2/Al using ultrasonic test