Результаты исследований: Научные публикации в периодических изданиях › статья › Рецензирование
Ultradisperse Composite Vitrified Host Materials of Monazite–Iron (Pyro)phosphate Type for Conservation of Nuclear Waste Concentrates. / Kuznetsov, R. A.; Kanterman, I. G.; Eremin, V. V.; Semenov, V. G.
в: Radiochemistry, Том 60, № 3, 01.05.2018, стр. 323-327.Результаты исследований: Научные публикации в периодических изданиях › статья › Рецензирование
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TY - JOUR
T1 - Ultradisperse Composite Vitrified Host Materials of Monazite–Iron (Pyro)phosphate Type for Conservation of Nuclear Waste Concentrates
AU - Kuznetsov, R. A.
AU - Kanterman, I. G.
AU - Eremin, V. V.
AU - Semenov, V. G.
PY - 2018/5/1
Y1 - 2018/5/1
N2 - A new type of a promising glassy-crystalline host material was prepared by ultradisperse synthesis in model experiments. The starting product is the nitric acid fraction of fission products (Cs, Sr, Ba), obtained radiochemically from irradiated nuclear fuel of a WWER-1000 reactor (1000-MWel water-cooled water-moderated energy reactor). Equivalent amounts of La(NO3)3, H3PO4, and Fe2O3 are added, and water is removed on heating. After complete removal of moisture, the residue is calcined at 600°С. The phosphated calcinate is dispersed in acetone to obtain slurry and, after removing acetone, converted to the glassy form at 950°С by self-igniting high-temperature synthesis. The whole process of preparing the composite is performed in one container crucible, which is then sealed. The major constituent of the host material is iron (pyro)phosphate glass (~55%); the finely grained crystalline phase, according to X-ray diffraction data, consists mainly of monazite of the composition La2(Sr,Ba)3(PO4)4. The monazite content is about 40%. Monazite forms with the glass via covalent bonding a composite exhibiting high corrosion resistance. The steady-state rate of Cs leaching form the monazite glass is 0.1 μg cm–2 day–1 (90°С, 100 days).
AB - A new type of a promising glassy-crystalline host material was prepared by ultradisperse synthesis in model experiments. The starting product is the nitric acid fraction of fission products (Cs, Sr, Ba), obtained radiochemically from irradiated nuclear fuel of a WWER-1000 reactor (1000-MWel water-cooled water-moderated energy reactor). Equivalent amounts of La(NO3)3, H3PO4, and Fe2O3 are added, and water is removed on heating. After complete removal of moisture, the residue is calcined at 600°С. The phosphated calcinate is dispersed in acetone to obtain slurry and, after removing acetone, converted to the glassy form at 950°С by self-igniting high-temperature synthesis. The whole process of preparing the composite is performed in one container crucible, which is then sealed. The major constituent of the host material is iron (pyro)phosphate glass (~55%); the finely grained crystalline phase, according to X-ray diffraction data, consists mainly of monazite of the composition La2(Sr,Ba)3(PO4)4. The monazite content is about 40%. Monazite forms with the glass via covalent bonding a composite exhibiting high corrosion resistance. The steady-state rate of Cs leaching form the monazite glass is 0.1 μg cm–2 day–1 (90°С, 100 days).
KW - conservation of nuclear waste concentrates
KW - iron (pyro)phosphate glass
KW - vitrified host material
KW - iron (pyro) phosphate glass
KW - IMMOBILIZATION
KW - CERAMICS
UR - http://www.scopus.com/inward/record.url?scp=85048241086&partnerID=8YFLogxK
U2 - 10.1134/S1066362218030165
DO - 10.1134/S1066362218030165
M3 - Article
AN - SCOPUS:85048241086
VL - 60
SP - 323
EP - 327
JO - Radiochemistry
JF - Radiochemistry
SN - 1066-3622
IS - 3
ER -
ID: 32864135