Powder characteristics and microstructure of uranium dioxide and uranium dioxide-gadolinium oxide fuel

被引：28

作者：

Gunduz, G ^{[1
]}

Uslu, I ^{[1
]}

机构：

[1] TURKIYE ATOM ENERJISI KURUMU,NUKL HESAPLAMALAR TASARIM GRUBU,TR-06100 BESEVLER,ANKARA,TURKEY

来源：

JOURNAL OF NUCLEAR MATERIALS | 1996年 / 231卷 / 1-2期

关键词：

D O I：

10.1016/0022-3115(96)00349-2

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Three different fuels UO2-only, UO2-Gd2O3(5%), and UO2-Gd2O3(10%) were produced by sol-gel technique. Their powder characteristics such as flowability, BET surface area, average pore diameter, and cumulative pore volume were determined. The pore size distributions of powders, green pellets, and sintered fuels were determined by using a mercury porosimeter. The theoretical densities of sintered fuels were found to be 98.01, 95.3, and 95.9%, respectively. Their ruggedness fractal dimensions were 1.111, 1.044, and 1.042, while the fractal dimensions associated with the size distribution of grains were 1.44, 1.58, and 1.60, respectively.

引用

页码：113 / 120

页数：8

共 26 条

[1]

FERGUSON DE, 1961, CEND1531, P23

[2] THE EFFECT OF GADOLINIUM CONTENT ON THE THERMAL-CONDUCTIVITY OF NEAR-STOICHIOMETRIC (U,GD)O2 SOLID-SOLUTIONS [J].

FUKUSHIMA, S ;

OHMICHI, T ;

MAEDA, A ;

WATANABE, H .

JOURNAL OF NUCLEAR MATERIALS, 1982, 105 (2-3) :201-210

[3] FRACTAL STRUCTURE OF GEL POROSITY [J].

GELLERI, B ;

SERNETZ, M .

ANALYTICA CHIMICA ACTA, 1984, 163 (SEP) :17-24

[4]

GUNDUZ G, 1995, NUCL TECHNOL, V111, P63

[5] PORE-SIZE DISTRIBUTIONS IN URANIUM-DIOXIDE AND URANIUM DIOXIDE-GADOLINIUM OXIDE FUEL KERNEL PRODUCED BY SOL-GEL TECHNIQUE [J].

GUNDUZ, G ;

ONAL, I ;

DURMAZUCAR, HH .

JOURNAL OF NUCLEAR MATERIALS, 1991, 178 (2-3) :212-216

[6]

HAAS PA, 1966, CAN J CHEM ENG DEC, P348

[7] THERMAL-DIFFUSIVITY OF UO2-GD2O3 PELLETS [J].

HIRAI, M .

JOURNAL OF NUCLEAR MATERIALS, 1990, 173 (03) :247-254

[8]

HIRAI M, 1991, J NUCL SCI TECHNOL, V28, P995, DOI 10.3327/jnst.28.995

[9] STRUCTURAL CHEMISTRY OF SOLID-SOLUTIONS IN THE UO2-GD2O3 SYSTEM [J].

HO, SM ;

RADFORD, KC .

NUCLEAR TECHNOLOGY, 1986, 73 (03) :350-360

[10]

*IAEA TECDOC, 1994, IAEATECDOC844

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