A double-layered model for near-field temperature in a nuclear waste repository

2021 ◽  
Vol 133 ◽  
pp. 103646
Author(s):  
Yao Xue ◽  
De'an Sun ◽  
Lei Wang ◽  
Yongfu Xu
Keyword(s):  
Nuclear Waste ◽  
Near Field ◽  
Nuclear Waste Repository ◽  
Layered Model ◽  
Field Temperature ◽  
Waste Repository

Semianalytical Solution to Near-Field Temperature in Nuclear Waste Repository

2020 ◽  
pp. 1-16
Author(s):  
Xiangyun Zhou ◽  
Annan Zhou ◽  
De’An Sun ◽  
Daichao Sheng
Keyword(s):  
Nuclear Waste ◽  
Near Field ◽  
Nuclear Waste Repository ◽  
Field Temperature ◽  
Waste Repository

scholarly journals Radiation Effects on Materials in the Near-Field of a Nuclear Waste Repository

2000 ◽  
Vol 663 ◽  
Author(s):  
B.X. Gu ◽  
L.M. Wang ◽  
S.X. Wang ◽  
R.C. Ewing
Keyword(s):  
Ion Exchange ◽  
Nuclear Waste ◽  
Radiation Effects ◽  
Ion Beam ◽  
Near Field ◽  
Energetic Electron ◽  
Layered Silicates ◽  
Nuclear Waste Repository ◽  
Layer Spacing ◽  
Waste Repository

ABSTRACTThe long-term radiation effects on materials in the near-field of a nuclear waste repository have been evaluated using accelerated laboratory experiments with energetic electron or ion beam irradiation. The materials studied include: zeolites, layered silicates (smectite clay and mica), as well as crystalline silicotitanate (CST) which is an important ion exchange material for the chemical separation of high-level liquid radioactive wastes.In situ transmission electron microscopy (TEM) during irradiation by energetic electrons and ions has shown that all of the studied materials are susceptible to irradiation-induced amorphization. At room temperature, complete amorphization was observed after ionizing doses of 1010 ∼ 1012 Gy or displacement doses on the order of 0.1 dpa (equivalent to doses received in 400-1,000 years for a high-loading nuclear waste form). Amorphization may be preceded or accompanied by dehydration, layer spacing reduction and gas bubble formation. In the case of zeolites, CST and some layered silicates, radiation effects are significantly enhanced at higher temperatures. Our experiments have shown that amorphization or even partial amorphization will cause a dramatic reduction in ion exchange and sorption/desorption capacities for radionuclides, such as Cs and Sr. Because the near-field or chemical processing materials (e.g. zeolites or CST) will receive a substantial radiation dose after they have incorporated radionuclides, our results suggest that radiation effects may, in some cases, retard the release of sorbed or ion-exchanged radionuclides.

In situ experiments on the performance of near-field for nuclear waste repository at KURT

2012 ◽  
Vol 252 ◽  
pp. 278-288 ◽  
Author(s):  
Won-Jin Cho ◽  
Jin-Sub Kim ◽  
Changsoo Lee ◽  
Sangki Kwon ◽  
Jong-Won Choi
Keyword(s):  
Nuclear Waste ◽  
Near Field ◽  
Nuclear Waste Repository ◽  
In Situ Experiments ◽  
Waste Repository

Implications of rock structure on the performance in the near field of a nuclear waste repository

1998 ◽  
Vol 49 (3-4) ◽  
pp. 195-200 ◽  
Author(s):  
Johan Andersson ◽  
Peter Robinson ◽  
Michael Impey
Keyword(s):  
Nuclear Waste ◽  
Near Field ◽  
Nuclear Waste Repository ◽  
Rock Structure ◽  
Waste Repository

Experimental Interaction of Basalt, Bentonite, and Water: Implications for Groundwater Chemistry in Waste Package Packing Material in a Nuclear Waste Repository

1987 ◽  
Vol 112 ◽  
Author(s):  
Gail L. McKeon ◽  
E. C. Thornton ◽  
D. J. Halko ◽  
M. I. Wood
Keyword(s):  
Nuclear Waste ◽  
Near Field ◽  
Sodium Concentration ◽  
Packing Material ◽  
Deionized Water ◽  
Solution Chemistry ◽  
Nuclear Waste Repository ◽  
Waste Package ◽  
Waste Repository ◽  
C 30

AbstractExperiments have been conducted by the Basalt Waste Isolation Project (BWIP) to assess changes in solution chemistry in the near-field environment of a nuclear waste repository in basalt. These Dickson autoclave experiments were carried out using Grande Ronde basalt ± bentonite and synthetic groundwater or deionized water at 300°C, 30 MPa, and solution-to-solid mass ratio of 10 for up to two years. Groundwater solution changes during reaction of the basalt and basalt/bentonite included initial decreases in pH and sodium concentration presumably due to smectite formation. This initial trend subsequently reversed in the basalt system with pH rising to ca. 7.5 and sodium increasing to the starting value. Steady state pH values for the basalt/bentonite system were ca. 6.4. The basalt + deionized water test exhibited a constant rise in pH to ca. 7.9 and release of sodium to solution in response to basalt dissolution. Slightly oxidizing conditions characterized the early part of all of the experiments followed by a decrease in fO2 to 10−31 to 10−32 These results are consistent with other work at similar and lower temperatures, suggesting that the packing material will react in the waste package environment to produce slightly alkaline, reducing conditions.

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