Scoping Thermal Analysis of Alternative Dual-Purpose Canister Disposal Concepts

Greenberg, H R; Wen, Jiang; Buscheck, Thomas A.

doi:10.2172/1090011

Cited by 8 publications

(6 citation statements)

References 3 publications

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“…The base heat curve assumes a single average pressurizedwater reactor (PWR) fuel assembly aged for 25 years before emplacement (Brady et al 2009) with an initial output of 580W/canister. Heat output vs. time is represented by the curves designed by Greenberg et al (2013). A second heat source is considered, with a higher initial heat output of 2,600W/canister, representative of reprocessed high-level waste aged 10 years before emplacement.…”

Section: Deep Borehole Field Test Research Activities At Lbnl August mentioning

confidence: 99%

Deep Borehole Field Test Research Activities at LBNL

Dobson¹,

Tsang²,

Kneafsey³

et al. 2016

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SUMMARYThe goal of the U.S. Department of Energy Used Fuel Disposition's (UFD) Deep Borehole Field Test is to drill two 5 km large-diameter boreholes: a characterization borehole with a bottom-hole diameter of 8.5 inches and a field test borehole with a bottom-hole diameter of 17 inches. These boreholes will be used to demonstrate the ability to drill such holes in crystalline rocks, effectively characterize the bedrock repository system using geophysical, geochemical, and hydrological techniques, and emplace and retrieve test waste packages. These studies will be used to test the deep borehole disposal concept, which requires a hydrologically isolated environment characterized by low permeability, stable fluid density, reducing fluid chemistry conditions, and an effective borehole seal.During FY16, Lawrence Berkeley National Laboratory scientists conducted a number of research studies to support the UFD Deep Borehole Field Test effort. This work included providing supporting data for the Los Alamos National Laboratory geologic framework model for the proposed deep borehole site, conducting an analog study using an extensive suite of geoscience data and samples from a deep (2.5 km) research borehole in Sweden, conducting laboratory experiments and coupled process modeling related to borehole seals, and developing a suite of potential techniques that could be applied to the characterization and monitoring of the deep borehole environment. The results of these studies are presented in this report.

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Section: Deep Borehole Field Test Research Activities At Lbnl August mentioning

confidence: 99%

Deep Borehole Field Test Research Activities at LBNL

Dobson¹,

Tsang²,

Kneafsey³

et al. 2016

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“…A drift of 5 m high by 7 m wide or a circular cross-section with a Used Fuel Disposal in Crystalline Rocks 14 9/26/2014 14 diameter of 5.5 m was proposed in the report. Greenberg et al (2013) did a series of thermal analyses for 32-PWR waste packages with a burnup of 40 GWd/MT and with different drift and waste package spacings and ventilation times. In the shale reference case, we assume a drift spacing of 70 m, waste package spacing of 20 m, and a ventilation time of 50 years.…”

Section: Repository Layoutmentioning

confidence: 99%

Used Fuel Disposal in Crystalline Rocks: Status and FY14 Progress.

Wang¹

2014

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Executive SummaryThe U.S. Department of Energy Office of Nuclear Energy, Office of Fuel Cycle Technology established the Used Fuel Disposition Campaign (UFDC) in fiscal year 2010 (FY10) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel and high level nuclear waste. The Mission of the UFDC isTo identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles.The work package of Crystalline Disposal R&D directly supports the following UFDC objectives: Develop a fundamental understanding of disposal system performance in a range of environments for potential wastes that could arise from future nuclear fuel cycle alternatives through theory, simulation, testing, and experimentation.  Develop a computational modeling capability for the performance of storage and disposal options for a range of fuel cycle alternatives, evolving from generic models to more robust models of performance assessment.The objective of the Crystalline Disposal R&D Work Package is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and computational capabilities to evaluate various disposal concepts in such media.Significant progress has been made in FY14 in both experimental and modeling arenas in evaluation of used fuel disposal in crystalline rocks. The work covers a wide range of research topics identified in the R&D plan. The major accomplishments are summarized below:  A R&D plan was developed for used fuel disposal in crystalline rocks. A total of 31 research topics (9 for system level and 22 for processes level) have been identified. The technical approach to addressing each of these topics is formulated.  A generic reference case for crystalline disposal media has been established. The reference case specifies the emplacement concept, waste inventory, waste form, waste package, backfill/buffer properties, EBS failure scenarios, host rock properties, and biosphere. This is an important step in developing a baseline for total system model development. Three emplacement concepts were specified: waste packages containing 4 PWR assemblies emplaced in boreholes in the floors of horizontal tunnels (for comparison with the KBS-3 concept), a 12-assembly waste package emplaced in tunnels, and a 32-assembly dual purpose canister emplaced in tunnels.  We have developed and applied THMC models to the analysis of coupled EBS processes in bentonite-backfilled repositories. We based this development on the extension of the Used Fuel Disposal in Crystalline Rocks vi 9/26/2014Used Fuel Disposal in Crystalline Rocks 9/26/2014 vii column method for evaluating and parameterizing colloid-facilitated radionuclide transport, using bentonite colloids, Am, and Grimsel Test Site granodiorite FFM as a model system. The method is designed to better interrogate the slowe...

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“…Schematic illustration of an emplacement drifts for an argillite-hosted repository . Note that Hardin et al (2013) determined drift and waste package spacing based on a thermal limit at the rock wall of 100 o C. In this report smaller spacing is used based on the scoping calculation by Greenberg et al (2013) Table 4. Mass fraction (%) of minerals for FEBEX (ENRESA 2000;Fernández et al 2004) and MX-80 bentonite (Börgesson et al 2006 Table 5.…”

Section: Figuresmentioning

confidence: 99%

“…Note that Hardin et al (2013) determined drift and waste package spacing based on a thermal limit at the rock wall of 100°C. In this report smaller spacing is used based on the scoping calculation by Greenberg et al (2013).…”

Section: Generic Argillite Repository Disposal Conceptmentioning

confidence: 99%

“…A drift 5 m high by 7 m wide or a circular cross-section with a diameter of 5.5 m was proposed in the report . Greenberg et al (2013) did a series of thermal analyses for 32-PWR waste packages with a burnup of 40 GWd/MT and with different drift and waste package spacings and ventilation times. In the reference case, we assume a drift spacing of 70 m, waste package spacing of 20 m, and ventilation time of 50 years.…”

Section: Layout For Dpcsmentioning

confidence: 99%

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