<trans-title>Radionuclides from Nature to Nature: Recent Progress in Immobilization of High Level Nuclear Wastes in SYNROC</trans-title>

Tao DUAN; Yi DING; Shilin LUO; Shengtai ZHANG; Jian LIU

doi:10.15541/jim20200247

Journal of Inorganic Materials, Volume. 36, Issue 1, 25(2021)

Radionuclides from Nature to Nature: Recent Progress in Immobilization of High Level Nuclear Wastes in SYNROC

Tao DUAN1... Yi DING1, Shilin LUO2, Shengtai ZHANG3 and Jian LIU1 |Show fewer author(s)

¹National Co-Innovation Center for Nuclear Waste Disposal and Environmental Safety, Southwest University of Science and Technology, Mianyang 621010, China

²Physics and Space Sciences College, China West Normal University, Nanchong 637002, China

³School of Materials Science and Engineering, Sichuan University of Science & Engineering, Zigong 643000, China;

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Figures & Tables(8)

1. Schematic diagram of pyrochlore structure and its ion occupation (A: Gd…, B: Zr…)

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2. Multiscale materials designed for extraction and confinement of radionuclides^[8]

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3. Model diagram of zirconia and silicon oxide reacting under the condition of 1500 ℃ and P^o to form zircon ball stick

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4. Temperature gradient model of zircon interface by using microwave synthesis^[32]

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5. Carbon thermal shock ultra-high temperature rapid sintering^[48]

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Table 1.
几种人造岩石固化体的化学成分

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Table 1.
几种人造岩石固化体的化学成分

SYNROC	Component mass fraction/%							Waste package capacity/%
SYNROC	TiO₂	UO₂	ZrO₂	Al₂O₃	SiO₂	BaO	CaO	Waste package capacity/%
SYNROC-B	74.1	-	6.6	5.4	-	5.6	11.0	-
SYNROC-C	57.1	-	5.4	4.4	-	4.4	8.9	30.0
SYNROC-D	18.8	-	6.6	-	6.6	-	5.3	62.7~65.0
SYNROC-E	87.6	-	3.0	-	-	-	2.2	7.0
SYNROC-F	40.6	47.6	-	0.9	1.1	9.5	-	50.0

Table 2.
辐照损伤的试验研究方法

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Table 2.
辐照损伤的试验研究方法

Irradiation method	Experimental program	Advantage	Disadvantage
Ion irradiation	Heavy ion beam bombardment	Irradiation damage at low level	Suppress vacancy defects
Electron irradiation	Accelerated voltage induction	Observe defect formation	Complex and expensive equipment
Neutron irradiation	Reactor irradiation	Large dosage, short time	Difficult to control temperature and dosage

Table 3.
高放废物不同固化方法

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Table 3.
高放废物不同固化方法

SYNROC	Typical components	Density/(g·cm^-3)	Strength	Long-term stability	Package capacity/wt%	Thermal conductivity /(W·m^-1·℃^-1)	Leaching rate /(g·cm^-2·d^-1)
Calcined product	CaF₂Al₂O₃ZrO₂	1.0-1.7	Powder	Unstable	High	0.13-0.20	0.1-10
Borosilicate glass	SiO₂B₂O₃Na₂OAl₂O₃	2.5-2.8	Hard and brittle	Yellow phase is formed, and there is a tendency to crystallize	15-30	1.00-1.50	10^-6-10^-4
Phosphate glass	P₂O₅Al₂O₃Na₂O	2.5-3.0	Hard and brittle	Large tendency to crystallize	15-30	1.00-1.50	10^-5-10^-3
Synroc	TiO₂ZrO₂CaOAl₂O₃BaO	4.0-5.8	Hard	Stable	15-30	2.50-3.50	10^-8-10^-5

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Tao DUAN, Yi DING, Shilin LUO, Shengtai ZHANG, Jian LIU. Radionuclides from Nature to Nature: Recent Progress in Immobilization of High Level Nuclear Wastes in SYNROC[J]. Journal of Inorganic Materials, 2021, 36(1): 25

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