25 herold impact of retrieval requirements
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This document discusses the impact of retrieval requirements on the design of radioactive waste repositories in Germany. By law, repositories must allow for the planned retrieval of radioactive waste containers during the operating period before final closure. The authors propose a "re-mining" strategy where sealed mine openings would be re-excavated to retrieve waste containers as required. They analyzed the operational processes, layout, equipment, and conditions expected during retrieval for two salt repository options - drift disposal of casks and borehole disposal of spent fuel canisters.
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The document summarizes Germany's new approach for siting a nuclear waste repository. It outlines a 5 stage process including site selection, mining development, waste emplacement, monitoring, and sealing. Stage 1 involves a 3 phase site selection process by 2031 to identify potential sites and choose a final location. Key organizations involved include the Federal Ministry for the Environment and the new Federal Organization for Nuclear Disposal. The Repository Commission established criteria for assessing potential host rocks like rock salt, claystone, and granite based on factors like isolation ability, safety, and competing land uses. Germany aims to ensure the best possible safety for radioactive waste storage over a period of 1 million years.
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This document summarizes a presentation on alternative disposal options for high-level radioactive waste. It discusses research being conducted from 2020-2023 on the state of science and technology for alternative disposal methods. Deep borehole disposal and long-term interim storage are examined in more detail. Deep borehole disposal could provide deeper isolation than mined repositories but lacks engineered barriers. Long-term interim storage for hundreds of years is an option but requires active maintenance and monitoring. Partitioning and transmutation is also summarized, which aims to reduce radioactive waste but does not eliminate the need for repositories and would be infeasible for Germany given its nuclear phase-out. The research so far indicates no major advances in alternative options since the topic was last evaluated
08 kuehnlenz kosina project
The KOSINA project was launched in 2015 by the German government to investigate bedded salt formations as a potential host rock for a nuclear waste repository. The project developed generic 3D geological models of two types of bedded salt formations - flat-bedded and salt pillow. These models incorporated available geological data on German salt formations and minimum requirements for depth and thickness of geological barriers. Based on the 3D models, the project defined two technical repository designs for flat-bedded salt and two for salt pillow. Results from the KOSINA project provide a basis for evaluating the safety of repository systems in different host rocks according to German regulations.
14 Radiological Consequences Analysis for a HLW Repository in Bedded Salt in ...
14 Radiological Consequences Analysis for a HLW Repository in Bedded Salt in ...Sandia National Laboratories: Energy & Climate: Renewables
The document summarizes radiological consequence analyses for a hypothetical high-level waste repository in bedded salt formations in Germany. It describes work packages analyzing the safety concept and developing a safety demonstration concept. Test cases are analyzed to verify applicability of radiological indicators and models. The base case scenario and sensitivity cases with reduced diffusion and convergence are modeled. Results show the repository system can provide long-term containment and negligible radiological impacts due to the geological barrier and engineered barriers like shaft and drift seals and compacted salt backfill. Sensitivity studies aid understanding key parameters and processes.shell_0
The document discusses Shell's Prelude FLNG project, the first floating liquefied natural gas facility in the world located offshore Australia. It describes how in 2009, Shell and the Technip-Samsung Consortium signed an agreement for the design, construction, and installation of multiple FLNG facilities over 15 years. Key milestones included starting construction in 2012 and completing the hull in 2013. The Prelude FLNG facility is expected to produce 3.6 million tonnes per year of LNG. Safety was a primary focus in the design of the facility to handle liquefied natural gas offshore.
Improving Efficiency Tight Gas
This white paper proposes a subsea separation system using cyclonic technology to improve the economic viability of developing tight, low reserve gas fields in the Southern North Sea. Computational fluid dynamics was used to verify that a cyclone unit could effectively separate solids from well fluids on the seabed. An accumulator would collect solid particles for removal by ROV, while a pipeline would transport separated gas to an offshore platform. Economic modeling indicated the proposed subsea system could reduce costs compared to conventional approaches, making marginal fields commercially feasible.
03 wolf safety case german approach
The document discusses the German approach to developing a safety case for a high-level radioactive waste repository. It describes how over several research projects, including ISIBEL and KOSINA, Germany has established a methodological approach to derive a safety concept and identify strategic measures to ensure safe containment within a containment-providing rock zone. A key element is a scenario development methodology to manage uncertainties and form the basis for safety assessments. The assessments analyze the integrity of geological and geotechnical barriers and the compaction of backfill materials. Potential radionuclide releases from the containment zone in scenarios are evaluated against radiological safety indicators.
Interactions 38: Startup UTC serie II
The document discusses six action groups that have been proposed by UTC's executive directorate and university board to address strategic issues facing UTC and build its future. The six themes identified for these groups are: 1) UTC's partnership environment and relations with other universities; 2) evolution of UTC's training offerings; 3) development of UTC's innovation mission; 4) increasing and diversifying UTC's financial resources; 5) developing UTC's research activities and PhD program; and 6) integrating digital technologies into UTC's strategic policies. The action groups will develop deliverables in 2016 to help reconcile UTC's values with market outputs without compromising values.
ISOPE-2010-TCP-0462 Lessons Learnt from deepwater Riser Projects
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CarbonNet storage site characterisation and selection process
The CarbonNet Project has undertaken an extensive geoscience evaluation programme to identify, characterise and select prospective offshore storage sites in the nearshore Gippsland Basin, in south eastern Australia.
The process builds upon basin and regional assessments undertaken at the national level, and focuses upon leads and play fairs assessed using a vast amount of geological data available from 50 years of petroleum exploration and developments in the basin.
CarbonNet geoscience work has been subject to independent scientific peer reviews, and external assurance certification by Det Norske Veritas against the recommended practise for geological storage of carbon dioxide (CO2) J203.
CarbonNet now holds five greenhouse gas assessments permits providing exclusive rights to explore, appraisal and develop a portfolio of CO2 storage sites.
The project has identified a prioritised storage site capable of storing in excess of 125 Mt of CO2 for which a 'Declaration of Storage' has been prepared which demonstrates the 'fundamental determinants' and probability assessment of potential CO2 plume paths as required under Australian CCS legislation'.
This webinar will be presented by Dr Nick Hoffman, CarbonNet Geosequestration Advisor, and will provide an overview of CarbonNet geoscience evaluation programme, referencing the relevant knowledge share products available on the Global CCS Institute website.
Cutting_edge_FRM_Article
The Cutty Sark ship underwent a major restoration project after being damaged by a fire in 2007. The project faced challenges due to the ship's historic status but implemented an innovative, fully fire-engineered approach. This included raising the ship above the dry berth, developing a fire strategy that considered life safety and heritage protection, and using computational modeling to evaluate fire risks and evacuation. The fire-engineered solutions allowed increased visitor capacity while protecting the Grade I listed ship.
184648009 new-hot-bitumen-storage-tank-construction-guidelines-march-2012-2
This document provides guidelines for designing, fabricating, and erecting new above-ground hot bitumen storage tanks. Key considerations include site layout, tank sizing, load design, safety equipment, and foundations. Hazards of working with hot bitumen include thermal burns, froth-overs, hydrogen sulfide formation, and ignition sources. Engineers should be consulted to design tanks that meet specifications and mitigate risks while storing bitumen at maximum temperatures of 260°C.
Health, Safety and Environment Aspects of Carbon dioxide Sequestration | By: ...
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Having a blast - MM Dec 2014
This document discusses blasting technologies used in surface mining. It describes how blast patterns are designed based on factors like rock properties and fragmentation needs. Different explosive combinations can be used depending on conditions like wet ground. Electronic detonators provide benefits like improved sequencing control. Research is working to develop models that can more accurately predict blast results and explosives that eliminate hazardous nitrogen oxide fumes from coal blasting.
19 herold shaft seals for hlw repositories
The document discusses shaft sealing concepts for nuclear waste repositories in rock salt or claystone host rocks. It summarizes tests conducted as part of the ELSA project to develop modular shaft sealing designs that can be adapted to site conditions. Bitumen/asphalt seals were tested in-situ and showed permeability close to initial host rock permeability, with bitumen penetrating cracks. In-situ tests of MgO-concrete and crushed salt/clay mixtures also demonstrated suitability for sealing. Bentonite seals showed potential functionality independent of host rock type.
Mg Innovation Flng Cn 2010 R1
This document summarizes an upcoming presentation on innovative ideas for light modules for FPSO and FLNG projects. The presentation will be given by Mukes Gupta of Canadoil Engineering on March 24th, 2010. It will discuss the current status and challenges of FPSO and FLNG projects, as well as innovative modularization approaches that can help address challenges and reduce costs. Specific topics to be covered include modularization benefits and pitfalls, case studies of different modularization projects, and innovative cost-saving methods for modularization.
Melbourne Channel Deepening
The Port of Melbourne Corporation proposed deepening shipping channels to allow larger vessels to access the port. This Channel Deepening Project involved dredging 22 million cubic meters of material. Boskalis was selected as the contractor due to their expertise in dredging techniques and environmental compliance. Their early involvement helped develop innovative dredging methods, protect underwater pipelines, and ensure the project met strict environmental standards. Through transparency and monitoring, the project was completed on time and within budget while avoiding environmental impacts.
2013 iea - potential for CO2 storage in oil gas shale reservoirs
The document discusses potential implications of gas production from shales and coals for geological storage of CO2. It finds that exploiting gas from shales and coals increases permeability and injectivity, potentially enhancing CO2 storage capacity. However, large-scale demonstration is still needed to confirm CO2 storage capabilities and capacities. Overlap between potential shale gas areas and saline aquifer storage sites may be considerable geographically but less so in 3D, so both resources could be used with care. Injectivity issues like coal swelling upon CO2 injection require further research.
art%3A10.1007%2Fs40789-016-0124-3
1) Nanocomposite sodalite/ceramic membranes were synthesized via a "pore-plugging" hydrothermal synthesis method for pre-combustion CO2 capture from coal-fired power plants.
2) Characterization of the membranes showed sodalite crystals embedded within the pores of the ceramic membrane support, forming a nanocomposite structure. This results in higher mechanical strength and thermal stability than conventional thin-film membranes.
3) The nanocomposite architecture also allows for defect control by limiting defects to the size of support pore openings, and protects the membrane from damage during use. This makes the membrane a promising material for high performance and cost-effective CO2 capture.
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19 Repository designs in bedded salt, the KOSINA-Project
19 Repository designs in bedded salt, the KOSINA-Project
Alternative Disposal Options for High-Level Radioactive Waste
Alternative Disposal Options for High-Level Radioactive Waste
14 Radiological Consequences Analysis for a HLW Repository in Bedded Salt in ...
14 Radiological Consequences Analysis for a HLW Repository in Bedded Salt in ...
ISOPE-2010-TCP-0462 Lessons Learnt from deepwater Riser Projects
ISOPE-2010-TCP-0462 Lessons Learnt from deepwater Riser Projects
CarbonNet storage site characterisation and selection process
CarbonNet storage site characterisation and selection process
184648009 new-hot-bitumen-storage-tank-construction-guidelines-march-2012-2
184648009 new-hot-bitumen-storage-tank-construction-guidelines-march-2012-2
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Health, Safety and Environment Aspects of Carbon dioxide Sequestration | By: ...
2013 iea - potential for CO2 storage in oil gas shale reservoirs
2013 iea - potential for CO2 storage in oil gas shale reservoirs
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43 international collaboration skb ebs task force overview jove-colon sand2...
This document summarizes work being done by the SKB Task Force related to modeling the engineered barrier system for a spent nuclear fuel repository. It discusses several tasks focused on thermomechanical modeling of bentonite clay buffer and backfill material using data from experiments at the Äspö Hard Rock Laboratory. The tasks aim to improve understanding and modeling of bentonite clay homogenization, water transport, gas transport, and the bentonite-rock interface using benchmarks from experiments. The ultimate goal is to better predict the long-term behavior of buffer/backfill materials under normal and abnormal conditions.
31 session corrosion of spent nuclear fuel canisters bryan sand2017 5541 pe
The document summarizes work related to corrosion of spent nuclear fuel canisters. It discusses experiments conducted at Sandia National Laboratories to study stress corrosion cracking of the canisters, including studies of brine stability, pitting damage quantification and the pit-to-crack transition process. It also outlines planned work for fiscal year 2018, including continued coupon tests under simulated storage conditions and microelectrochemical mapping of stressed samples to study the effects of stress on corrosion susceptibility.
27 task f fluid inclusion and movement in tight rocks wang sand2017-4132 pe...
Sandia National Laboratories researched fluid inclusion and movement in tight rocks. They used modeling and experiments to understand how fluid inclusions migrate under thermal gradients and how their shape and movement are affected by factors like inclusion size, thermal gradient, solubility, and permeability of the surrounding rock. Their goal is to better understand how fluids can move even in very tight rocks and how this movement may impact issues like waste isolation.
13 ensa enun 32 p rail cask transport tests start june 2017 mcconnell sand201...
Sandia National Laboratories and Pacific Northwest National Laboratory are conducting tests of a Spanish-designed spent nuclear fuel transport cask to collect data on stresses to the spent fuel during normal transport conditions. Tests will include transport by heavy-haul truck, ship, and rail in both the U.S. and Europe between June and August 2017. Instrumented mock fuel assemblies will collect strain and acceleration data during all transport stages and mode transfers. The data will help validate that spent fuel integrity is maintained during normal transport vibrations and impacts.
03 dry cask simulator experiments for cfd validation durbin sand2017 4330 c
Sandia National Laboratories conducted experiments using a Dry Cask Simulator (DCS) to validate computational fluid dynamics (CFD) models for spent nuclear fuel storage cask thermal analyses. The DCS uses a scaled prototype boiling water reactor assembly inside a pressure vessel to simulate internal conditions of dry casks. Thermocouples measure temperature profiles under various decay heat and helium pressure conditions to model aboveground and belowground cask storage. Initial testing of the aboveground configuration showed good agreement between experimental temperature measurements and CFD simulations, within estimated uncertainties.
17 laboratory testing approach for intermediate scale borehole heater test mi...
Sandia National Laboratories is preparing to conduct laboratory testing and analysis related to an intermediate scale borehole heater test. The testing will involve analyzing rock core samples, gases, and brines before, during, and after the test to observe the effects of heating. Specific analyses will include measuring core properties like porosity and pore size, as well as analyzing gas and brine compositions through techniques like gas chromatography, ion chromatography, and ICP-MS. Preliminary brine analysis of three samples found them to have a Na-Mg-Cl composition typical of WIPP brines. The laboratory work aims to provide detailed data on material interactions and micro-mechanical processes during heating to inform long-term repository performance.
10 sfwst – disposal in argillite r&d barrier material degradation and int...
The document summarizes research being conducted by Sandia National Laboratories and Los Alamos National Laboratories on disposal of nuclear waste in deep geologic repositories. It discusses several modeling and experimental efforts, including reactive transport modeling to study the effects of decay heat on engineered barrier systems, clay interaction experiments to understand clay-metal interactions during corrosion of waste packages, and international collaborations on projects like FEBEX-DP to characterize the bentonite-concrete interface using X-ray computed tomography. It also summarizes preliminary thermodynamic modeling of steel corrosion and reactive transport modeling of the Closure Test Drift to simulate cement-water interactions.
07 international collaboration activities in disposal r and d relevance to r ...
1) The document discusses DOE's participation in various international R&D collaborations related to nuclear waste disposal, including projects in Switzerland, Sweden, Germany, China, and other countries.
2) These collaborations support the GDSA program by furthering scientific understanding of key disposal processes, improving process models, and providing data to validate GDSA models.
3) Specific collaborations discussed include the Mont Terri project, DECOVALEX, SKB task forces, and a planned HotBENT project, with details provided on how they contribute to modeling and understanding disposal system behavior.
59 an example of a regional geologic evaluation of argillite for disposal of ...
The document summarizes a regional geologic evaluation of the Pierre Shale formation for its potential to host a repository for high-level radioactive waste and spent nuclear fuel. The Pierre Shale has desirable properties like its depth, large extent, high clay content, and stable tectonic setting. The evaluation assesses available data on the formation's stratigraphy, hydrogeology, seismic activity, and other features to evaluate its suitability for long-term repository performance. The Pierre Shale is representative of clay-rich Cretaceous formations that warrant further review for a deep geologic repository.
51 update on the fifth worldwide review international approaches for nuclear ...
The document summarizes a recently released report on international approaches for nuclear waste disposal in geological formations. It describes the content of the report, which reviews the status of scientific and technical advances as of 2016 in nuclear waste disposal programs in 23 countries. It also provides information on how to access the full report online or from the websites listed. Finally, it briefly describes a workshop held in 2016 to discuss the report, noting that it involved participants from 12 countries who presented on waste disposal programs in 21 countries.
49 collaboration with swedish deep drilling project dobson lbnl
This document discusses collaboration between Lawrence Berkeley National Laboratory and Uppsala University on the Swedish Deep Drilling Project (COSC). The COSC project aims to drill two deep boreholes (COSC-1 and COSC-2) to study geological structures and characterize basement rocks and hydrology. COSC-1 will drill through the Seve Nappe to study channel flow, reaching a depth of 2.5 km with 100% core recovery. Funded activities for COSC-1 include logging the borehole to detect flowing fractures, modeling fluid flow, analyzing microbial communities in fractures, characterizing water compositions, and studying fractured core samples.
46 collaboration with clausthal germany on coupled thm modeling rutqvist lbnl
This document summarizes a collaboration between Lawrence Berkeley National Laboratory and Clausthal University on coupled thermo-hydro-mechanical (THM) modeling of salt. It discusses the TOUGH-FLAC and FLAC-TOUGH simulators, benchmarking results, improvements made to both codes, and an example collaboration project modeling heater tests at the Asse mine. The collaboration has improved salt THM modeling through code comparisons and jointly developing new constitutive models.
34 ciscc susceptibility and cgr testing sindelar srnl sti-2017-00323
1) Testing was conducted on teardrop-shaped samples of 304L stainless steel exposed to salt/dust mixtures to evaluate chloride-induced stress corrosion cracking (CISCC) susceptibility and crack growth rates (CGRs).
2) Visual indications of pitting and preliminary CGRs around 0.5 mm/year were observed. Additional testing is needed to better characterize cracking and the influence of sensitization.
3) Residual stresses from welding were identified as a potential driving force for CISCC in spent nuclear fuel canisters. Remote visual examination techniques may have limitations for cracking detection.
4) There is currently no consensus on an ASME code case for canister in-service inspection due to open questions around
33 residual stress simulation and experimental stress replication of mock up ...
This document discusses simulations and experiments related to residual stress and stress corrosion cracking in welded mock-ups. It summarizes residual stress simulations of circumferential and longitudinal welds using finite element analysis and compares results to experimental measurements. It also describes the design of four-point bend experiments using finite element simulations to replicate stress conditions and digital image correlation experiments to validate simulations. The purpose is to model stress corrosion cracking using multiphysics finite element analysis.
32 field test at maine yankee independent spent fuel storage instillation gor...
The document summarizes a field test being conducted at the Maine Yankee Independent Spent Fuel Storage Installation to study chloride deposition and stress corrosion cracking of stainless steel canisters containing spent nuclear fuel. Small specimens will be placed in the air circulation vents of four dry storage canisters and monitored over time to evaluate environmental conditions and potential canister degradation. Analysis indicates the small amount of vent blockage caused by the specimens will not significantly impact temperatures or be considered an off-normal condition. The results are intended to help understand long-term aging of the canister material.
30 fe heater test at mont terri rutqvist lbnl
The document summarizes the Full-scale Emplacement (FE) Experiment being conducted at Mont Terri, Switzerland. The experiment involves heating three heaters embedded in a buffer of bentonite clay and surrounded by instrumented Opalinus clay host rock. The goals are to test the performance of a geological disposal system and monitor thermal, hydrological, mechanical, and chemical processes. International modeling teams are benchmarking models against experimental data. Initial modeling matches observed temperature and moisture profiles well using a reduced vapor diffusion coefficient. Continued monitoring and interpretive modeling will focus more on mechanical stresses developing from swelling and thermal effects over the multi-year experiment.
29 international collaboration in disposal research fs experiment at mont ter...
The document summarizes an experiment conducted at the Mont Terri rock laboratory in Switzerland to study the potential for leakage along faults intersecting an underground radioactive waste repository. The experiment involved injecting water into a borehole intersecting a fault to incrementally increase pressure and monitor permeability changes, seismic activity, and deformation. Seismic events up to magnitude -2.5 were observed during one injection stage when pressure exceeded the strength of the fault-damage zone interface. Analysis showed 75% of fault movement was aseismic and a large pressure drop preceded seismic slip events. Future work includes studying how distant earthquakes may impact fault permeability and long-term injection tests.
28 international collaboration in disposal research mont terri project birkho...
The Mont Terri Project is an international research project studying clay and shale formations for radioactive waste disposal. It provides access to an underground rock laboratory and experimental data from experiments addressing various factors important for disposal. Current and upcoming experiments include studies of thermomechanical-hydrological effects, bentonite and clay barrier performance, gas leakage, diffusion of radionuclides, and cement-clay interactions. The project recently celebrated its 20th anniversary and plans to expand the underground rock laboratory for new experiments.
27b potential hot bent collaboration zheng v0 lbnl
The document discusses a potential collaboration called HotBENT to conduct a joint experiment at the Grimsel Test Site to evaluate the behavior of clay buffers at temperatures of 150-200°C. The experiment would provide data on clay properties at high temperatures that are limited in current models. Partners like NAGRA are interested to justify higher design temperatures that reduce costs and to ensure most of the clay buffer remains intact. A proposed experiment involves placing bentonite in the old FEBEX tunnel at Grimsel up to 200°C to study moisture transport and swelling properties over 5 years.
27a febex dp collaboration overview and related sfwst r and d activities zhen...
The document summarizes research from the FEBEX-DP collaboration studying the full-scale FEBEX bentonite experiment located in Grimsel, Switzerland. It discusses characterization of the bentonite following dismantling of heater #2, including changes to density, water content, mineralogy, and pore water chemistry. THM and THMC models were developed and validated against experimental data to analyze thermal-hydrological-mechanical and chemical processes. Microstructural analysis using synchrotron X-ray microCT provided 3D characterization of the bentonite microstructure. Further work is focused on refining chemical models, analyzing gas evolution and microbial activity, and characterizing the bentonite-concrete interface.
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43 international collaboration skb ebs task force overview jove-colon sand2...
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31 session corrosion of spent nuclear fuel canisters bryan sand2017 5541 pe
31 session corrosion of spent nuclear fuel canisters bryan sand2017 5541 pe
27 task f fluid inclusion and movement in tight rocks wang sand2017-4132 pe...
27 task f fluid inclusion and movement in tight rocks wang sand2017-4132 pe...
13 ensa enun 32 p rail cask transport tests start june 2017 mcconnell sand201...
13 ensa enun 32 p rail cask transport tests start june 2017 mcconnell sand201...
03 dry cask simulator experiments for cfd validation durbin sand2017 4330 c
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17 laboratory testing approach for intermediate scale borehole heater test mi...
17 laboratory testing approach for intermediate scale borehole heater test mi...
10 sfwst – disposal in argillite r&d barrier material degradation and int...
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07 international collaboration activities in disposal r and d relevance to r ...
07 international collaboration activities in disposal r and d relevance to r ...
59 an example of a regional geologic evaluation of argillite for disposal of ...
59 an example of a regional geologic evaluation of argillite for disposal of ...
51 update on the fifth worldwide review international approaches for nuclear ...
51 update on the fifth worldwide review international approaches for nuclear ...
49 collaboration with swedish deep drilling project dobson lbnl
49 collaboration with swedish deep drilling project dobson lbnl
46 collaboration with clausthal germany on coupled thm modeling rutqvist lbnl
46 collaboration with clausthal germany on coupled thm modeling rutqvist lbnl
34 ciscc susceptibility and cgr testing sindelar srnl sti-2017-00323
34 ciscc susceptibility and cgr testing sindelar srnl sti-2017-00323
33 residual stress simulation and experimental stress replication of mock up ...
33 residual stress simulation and experimental stress replication of mock up ...
32 field test at maine yankee independent spent fuel storage instillation gor...
32 field test at maine yankee independent spent fuel storage instillation gor...
29 international collaboration in disposal research fs experiment at mont ter...
29 international collaboration in disposal research fs experiment at mont ter...
28 international collaboration in disposal research mont terri project birkho...
28 international collaboration in disposal research mont terri project birkho...
27b potential hot bent collaboration zheng v0 lbnl
27b potential hot bent collaboration zheng v0 lbnl
27a febex dp collaboration overview and related sfwst r and d activities zhen...
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みなさんこんにちはこれ何文字まで入るの？40文字以下不可とか本当に意味わからないけどこれ限界文字数書いてないからマジでやばい文字数いけるんじゃないの？えこ...
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25 herold impact of retrieval requirements
- 1. Impact of retrieval requirements on repository design Philipp Herold, Sabine Dörr, Eric Kuate Simo, Wilhelm Bollingerfehr, Wolfgang Filbert 7th US/German Workshop on Salt Repository Research, Design and Operation Washington, DC September 7-9, 2016 ABSTRACT In 2010, the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety issued the “Safety Requirements Governing the Final Disposal of Heat-Generating Radioactive Waste” (BMU, 2010). Since then, retrievability is a design criterion and a requirement for the licensing of HLW and spent fuel repository in Germany. All repository concepts have to ensure that retrieval of the waste containers is possible. In Germany, retrievability "… is the planned technical option for removing emplaced radioactive waste containers from the repository mine” (BMU, 2010) and must be possible during the operating period of a repository, which ends with the sealing of the shafts. The safety requirements also stipulate that the number of mine openings be kept to a minimum and that they be backfilled and sealed as soon as possible. Taking into account these design criteria, DBE TECHNOLOGY GmbH considers the so-called "re-mining" strategy as most suitable for the retrieval of waste containers. Emplacement of the waste containers and sealing of the mine openings is to be carried out as designed in the existing concepts, however, for retrieval, i.e. the removal of the waste containers from the repository, the already backfilled and sealed mine openings will be excavated again. Based on this strategy, DBE TECHNOLOGY GmbH investigated the operational processes during retrieval, the necessary mine layout and technical equipment as well as the expected underground conditions for the two disposal options in rock salt – drift disposal of POLLUX® casks and borehole disposal of spent fuel canisters (BSK).