High-Level Radioactive Waste Storage Feasibility for the Kingdom of Saudi Arabia

2014 ◽  
Vol 40 (1) ◽  
pp. 195-203 ◽  
Author(s):  
Dheya Shujaa Al-Othmany ◽  
Ahmad Hussain ◽  
Essam Banoqitah
2018 ◽  
Vol 119 ◽  
pp. 106-116 ◽  
Author(s):  
Shuliang Zou ◽  
Ya Kuang ◽  
Dewen Tang ◽  
Zan Guo ◽  
Shoulong Xu

2011 ◽  
Vol 94-96 ◽  
pp. 887-891
Author(s):  
Xin Zheng Wang ◽  
Jian Jie Chen ◽  
Guang Ping Zou ◽  
Li Ping

On the basis of analyzing the special requirements for security for the high-level radioactive waste storage structure, the seismic design parameters of this engineering are determined. There is no criterion that determines the design ground motion parameters of underground engineering. Based on the thought of the severest design ground motion, the basic methods and principles to determine the design ground motion parameters of underground structure are put forward. The characteristics of high-level radioactive waste storage structure are analyzed, and the frequencies corresponding to the maxim modal participation factors are gain. Combined with the analysis of the site geological safety assessment report, through the initial search and optimization with the method of numerical simulation, the design ground motion parameters of the high-level radioactive waste storage structure on the specific site is determined. The method is easy to operate, which can also be applied in other important deep underground engineerings.


1985 ◽  
Vol 49 (351) ◽  
pp. 195-201 ◽  
Author(s):  
David Savage ◽  
Jane E. Robbins ◽  
Richard J. Merriman

AbstractA borosilicate glass, containing 25 wt. % of simulated high-level radioactive waste has been reacted with water at 350°C and 500 bars for 14 and 48 days using large-volume ‘cold-seal’ high-pressure equipment. Under these conditions the glass crystallizes a suite of mineral phases including: albite, NaAlSi3O8; aegirine, NaFeSi2O6; riebeckite, Na2Fe2(Fe,Mg)3Si8O22(OH)2; zektzerite, LiNaZrSi6O15; barium-strontium molybdate, (Ba,Sr)MoO4; stillwellite, (Nd,Ce,La)BSiO5; willemite, Zn2SiO4; smectite; a lithium-sodium borosilicate hydrate; melilite (åkermanite), Ca2MgSi2O7. A description of the morphology of these phases is given, together with a number of chemical analyses. The implications of the incorporation of waste species in these mineral phases to the disposal of high-level radioactive waste is discussed.


Author(s):  
J. B. Elder ◽  
B. J. Wiersma ◽  
R. L. Sindelar

Several of the high level radioactive waste storage tanks at the Savannah River Site (SRS) have been in service nearly 50 years. Periodic visual and ultrasonic (UT) nondestructive examinations (NDE) have been performed on the tanks to monitor the effects of service. These inspections revealed that several of the older tanks had suffered cracking as detected by through-wall visual indications. A new UT in-service inspection program has been recently established to provide for detection and characterization of cracking, thinning, or pitting of the sidewalls of the waste tanks. The program specifies examination of regions of the tank that would be most susceptible to corrosion attack, and to characterize the flaws and demonstrate acceptance to protect against potential leakage and instability. This paper summarizes the implementation of the program and inspection results for a tank that has been in service for over 40 years. No indications of reportable wall loss or pitting were detected. All thickness readings were above minimum design thickness. Several small indications of thinning were detected. The crack detection and sizing examinations detected five previously undetected indications, four of which were only partially through wall. The lengths of cracks that were examined are slightly longer than expected, but well below instability lengths.


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