Problems and perspectives of borehole disposal of radioactive waste

Kochkin, B. T.; Malkovsky, V. I.; Yudintsev, S. V.; Петров, В. А.; Ojovan, Michael I.

doi:10.1016/j.pnucene.2021.103867

Cited by 24 publications

(16 citation statements)

References 22 publications

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“…Концепция ГСЗ с ее принципами обеспечения безопасности может быть реализована только в действительно глубоких скважинах . С предложением концепции латеральных скважин в проектах скважинного захоронения наметился переход от концепции сверхглубоких скважин в кристаллических породах фундамента к концепции горизонтальных ветвящихся скважин в породах осадочного чехла, согласно которой проекты размещения по геологическим условиям и своей геометрии выработок уже мало отличаются от шахтных хранилищ в пластичных породах [2] .…”

Section: концепция изоляции рао в глубоких скважинахunclassified

“…Организации по обращению с отходами и научные учреждения разных стран периодически проводят обзор и анализ осуществимости различных концепций удаления радиоактивных отходов (РАО) и отработавшего ядерного топлива (ОЯТ) в геологическую среду . На сегодня в мировой литературе между собой сравниваются, по крайней мере, три концепции геологической изоляции РАО: шахтные хранилища (ШХ), глубокое скважинное захоронение (ГСЗ/Deep Borehole Disposal) и захоронение в латеральных глубоких скважинах (ЛСЗ/Disposal in Horizontal Drillholes) [1][2][3] . ГСЗ подчас представляется как социально более приемлемая альтернатива ШХ, консенсус в отношении перспективности которой начал складываться еще 1960-х годах [4] .…”

Section: Introductionunclassified

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Borehole RW Disposal Concept and Prospects of its Implementation in Russia

Kochkin¹,

Bogatov²

2022

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Section: концепция изоляции рао в глубоких скважинахunclassified

Section: Introductionunclassified

Borehole RW Disposal Concept and Prospects of its Implementation in Russia

Kochkin¹,

Bogatov²

2022

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“…1 Source: [64] (Table C-1, for an initial enrichment of 4.73%, a burn-up of 60 gigawatt days per metric ton of initial heavy metals (GWd/MTIHM), and a cooling time of 30 years). 2 There are 0.435 metric tons of initial heavy metals (MTIHM) per pressurized water reactor assembly [28] (Activity A (Bq) is calculated as A = λN , where λ = ln(2)/t 1/2 (s −1 ) is the decay constant with t 1/2 (s) being the half-life, N = (m/MW)•N A is the number of decaying particles, where m (g) is the inventory mass, MW (g mol −1 ) is the molecular weight, and N A = 6.022×10 23 (mol −1 ) is the Avogadro number. 4 Source: [41] ( Example Reference Biosphere 1A); the dose coefficient listed includes the contributions from relatively short-lived daughters, assuming they are in secular equilibrium with the parent.…”

Section: Radionuclide Inventory and Waste Mobilizationmentioning

confidence: 99%

“…These differences are related to all aspects of repository design and operation, including pre-and post-closure safety as well as socio-economic considerations [15,21]. Some of these similarities and differences are described in [10,11,15,17,[22][23][24] and will be further discussed below.…”

Section: Introductionmentioning

confidence: 99%

Post-Closure Safety Analysis of Nuclear Waste Disposal in Deep Vertical Boreholes

Finsterle¹,

Muller

Grimsich

et al. 2021

Energies

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Isolation of spent nuclear fuel assemblies in deep vertical boreholes is analyzed. The main safety features of the borehole concept are related to the repository’s great depth, implying (a) long migration distances and correspondingly long travel times, allowing radionuclides to decay, (b) separation of the repository from the dynamic hydrological cycle near the land surface, (c) stable geological and hydrogeological conditions, and (d) a geochemically reducing environment. An integrated simulation model of the engineered and natural barrier systems has been developed to examine multiple scenarios of the release of radionuclides from the waste canisters, the transport through a fractured porous host rock, and the extraction of potentially contaminated drinking water from an aquifer. These generic simulations include thermal effects from both the natural geothermal gradient and the heat-generating waste, the influence of topography on regional groundwater flow, moderated by salinity stratification at depth, and the role of borehole sealing. The impact of these processes on the transport of select radionuclides is studied, which include long-lived, soluble, sorbing or highly mobile isotopes along with a decay chain of safety-relevant actinide metals. The generic analyses suggest that a deep vertical borehole repository has the potential to be a safe option for the disposal of certain waste streams, with the depth itself and the stable hydrogeological environment encountered in the emplacement zone providing inherent long-term isolation, which allows for reduced reliance on a complex engineered barrier system.

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“…Underground nuclear waste disposal may occur in mined tunnels and caverns at a depth of a few hundred meters [1,2] or in vertical boreholes at depths up to several kilometres [3,4]. The host rock in which these geologic disposal facilities (GDF) are being developed may be either a lower strength sedimentary rock such as clay [5] or a higher strength rock such as granite [6].…”

Section: Introductionmentioning

confidence: 99%

Coupled Heat-Mass Transport Modelling of Radionuclide Migration from a Nuclear Waste Disposal Borehole

Lari

Mallants

2022

Geofluids

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Disposal of radioactive waste originating from reprocessing of spent research reactor fuel typically includes stainless steel canisters with waste immobilised in a glass matrix. In a deep borehole disposal concept, waste packages could be stacked in a disposal zone at a depth of one to potentially several kilometres. This waste will generate heat for several hundreds of years. The influence of combining a natural geothermal gradient with heat from decaying nuclear waste on radionuclide transport from deep disposal boreholes is studied by implementing a coupled heat-solute mass transport modelling framework, subjected to depth-dependent temperature, pressure, and viscosity profiles. Several scenarios of waste-driven heat loads were investigated to test to what degree, if any, the additional heat affects radionuclide migration by generating convection-driven transport. Results show that the heat output and the calculated radioactivity at a hypothetical near-surface observation point are directly correlated; however, the overall impact of convection-driven transport is small due to the short duration (a few hundred years) of the heat load. Results further showed that the calculated radiation dose at the observation point was very sensitive to the magnitude of the effective diffusion parameter of the host rock. Coupled heat-solute mass transport models are necessary tools to identify influential processes regarding deep borehole disposal of heat-generating long-lived radioactive waste.

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Problems and perspectives of borehole disposal of radioactive waste

Cited by 24 publications

References 22 publications

Borehole RW Disposal Concept and Prospects of its Implementation in Russia

Borehole RW Disposal Concept and Prospects of its Implementation in Russia

Post-Closure Safety Analysis of Nuclear Waste Disposal in Deep Vertical Boreholes

Coupled Heat-Mass Transport Modelling of Radionuclide Migration from a Nuclear Waste Disposal Borehole

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