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Preparation of low-temperature sintered UO2 nanomaterials by radiolytic reduction of ammonium uranyl tricarbonate

  • Published:2016-10 Issue: Volume:479 Page:162-166
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Wang Yongming,Chen Qingde,Shen Xinghai

Funder

National Natural Science Foundation of China

Doctored Program of Higher Education of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference29 articles.

1. Identification of industrial furnace temperature for sintering process in nuclear fuel fabrication using NARX neural networks;Sutarya;Sci. Technol. Nucl. Install.,2014

2. The industrial practice of AUC process for producing ceramic UO2 in China;Zhu;China Nucl. Sci. Technol. Rep.,2000

3. The possible usage of ex-ADU uranium dioxide fuel pellets with low-temperature sintering;Ayaz;J. Nucl. Mater,2000

4. UO2 sintering in controlled oxygen atmospheres of three-stage process;Harada;J. Nucl. Mater,1997

5. Synthesis of colloidal uranium-dioxide nanocrystals;Wu;J. Am. Chem. Soc.,2006

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