Academic literature on the topic 'Nuclear disposal'

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Journal articles on the topic "Nuclear disposal"

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Latterich, M. "Nuclear waste disposal." Trends in Cell Biology 8, no. 7 (December 1998): 263. http://dx.doi.org/10.1016/s0962-8924(98)01308-7.

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Imada, Takatoshi. "On Nuclear Waste Disposal." Journal of the Atomic Energy Society of Japan 59, no. 5 (2017): 263–67. http://dx.doi.org/10.3327/jaesjb.59.5_263.

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Muller, Richard A., Stefan Finsterle, John Grimsich, Rod Baltzer, Elizabeth A. Muller, James W. Rector, Joe Payer, and John Apps. "Disposal of High-Level Nuclear Waste in Deep Horizontal Drillholes." Energies 12, no. 11 (May 29, 2019): 2052. http://dx.doi.org/10.3390/en12112052.

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Spent nuclear fuel and high-level radioactive waste can be disposed in deep horizontal drillholes in sedimentary, metamorphic or igneous rocks. Horizontal drillhole disposal has safety, operational and economic benefits: the repository is deep in the brine-saturated zone far below aquifers in a reducing environment of formations that can be shown to have been isolated from the surface for exceedingly long times; its depth provides safety against inadvertent intrusion, earthquakes and near-surface perturbations; it can be placed close to the reactors and interim storage facilities, minimizing transportation; disposal costs per ton of waste can be kept substantially lower than for mined repositories by its smaller size, reduced infrastructure needs and staged implementation; and, if desired, the waste could be retrieved using “fishing” technology. In the proposed disposal concept, corrosion-resistant canisters containing unmodified fuel assemblies from commercial reactors would be placed end-to-end in up to 50 cm diameter horizontal drillholes, a configuration that reduces mechanical stresses and keeps the temperatures below the boiling point of the brine. Other high-level wastes, such as capsules containing 137Cs and 90Sr, can be disposed in small-diameter horizontal drillholes. We provide an overview of this novel disposal concept and its technology, discuss some of its safety aspects and compare it to mined repositories and the deep vertical borehole disposal concept.
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Singer, S. Fred. "High-Level Nuclear Waste Disposal." Science 234, no. 4773 (October 10, 1986): 127–28. http://dx.doi.org/10.1126/science.234.4773.127.c.

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Singer, S. Fred. "High-Level Nuclear Waste Disposal." Science 234, no. 4773 (October 10, 1986): 127–28. http://dx.doi.org/10.1126/science.234.4773.127-c.

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Bella, David A., Charles D. Mosher, and Steven N. Calvo. "Establishing Trust: Nuclear Waste Disposal." Journal of Professional Issues in Engineering 114, no. 1 (January 1988): 40–50. http://dx.doi.org/10.1061/(asce)1052-3928(1988)114:1(40).

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Hurtley, S. M. "CELL BIOLOGY: Nuclear Waste Disposal." Science 308, no. 5721 (April 22, 2005): 468b. http://dx.doi.org/10.1126/science.308.5721.468b.

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Flowers, R. H. "Radioactivity and nuclear waste disposal." Journal of Environmental Radioactivity 7, no. 1 (January 1988): 93–95. http://dx.doi.org/10.1016/0265-931x(88)90045-8.

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Shrader-Frechette, Kristin. "Equity and nuclear waste disposal." Journal of Agricultural and Environmental Ethics 7, no. 2 (September 1994): 133–56. http://dx.doi.org/10.1007/bf02349034.

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SINGER, S. F. "High-Level Nuclear Waste Disposal." Science 234, no. 4773 (October 10, 1986): 127–28. http://dx.doi.org/10.1126/science.234.4773.127-b.

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Dissertations / Theses on the topic "Nuclear disposal"

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Hoag, Christopher Ian. "Canister design for deep borehole disposal of nuclear waste." Thesis, (5 MB), 2006. http://handle.dtic.mil/100.2/ADA473223.

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Thesis (M.S. in Nuclear Science and Engineering)--Massachusetts Institute of Technology, 2006.
"May 2006." Description based on title screen as viewed on June 1, 2010. DTIC Descriptor(s): Boreholes, Radioactive Wastes, Disposal, Canisters, Thermal Properties, USSR, Diameters, Thickness, Stability, Permeability, Environments, Corrosion, Drilling, Flooding, Storage, Reactor Fuels, Nuclear Energy, Barriers, Emplacement, Internal, Fuels, Igneous Rock, Geothermy, Drills, Hazards, Performance (Engineering), Water, Theses, Granite, Steel, Containment (General). Includes bibliographical references (p. 122-125). Also available in print.
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Taiyabi, Asif A. "A multi-attribute analysis of nuclear waste disposal alternatives." Master's thesis, This resource online, 1991. http://scholar.lib.vt.edu/theses/available/etd-02022010-020127/.

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Hoag, Christopher Ian. "Canister design for deep borehole disposal of nuclear waste." Thesis, Massachusetts Institute of Technology, 2005. http://hdl.handle.net/1721.1/41269.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, June 2006.
Includes bibliographical references (p. 122-125).
The objective of this thesis was to design a canister for the disposal of spent nuclear fuel and other high-level waste in deep borehole repositories using currently available and proven oil, gas, and geothermal drilling technology. The canister is suitable for disposal of various waste forms, such as fuel assemblies and vitrified waste. The design addresses real and perceived hazards of transporting and placing high-level waste, in the form of spent reactor fuel, into a deep igneous rock environment with particular emphasis on thermal performance. The proposed boreholes are 3 to 5 km deep, in igneous rock such as granite. The rock must be in a geologically stable area from a volcanic and tectonic standpoint, and it should have low permeability, as shown in recent data taken from a Russian deep borehole. Although deep granite should remain dry, water in flooded boreholes is expected to be reducing, but potentially corrosive to steel. However, the granite and plug are the containment barrier, not the canister itself. The canisters use standard oil drilling casings. The inner diameter is 315.32mm in order to accommodate a PWR assembly with a width of 214mm. At five meters tall, each canister holds one PWR assembly. The canister thickness is 12.19mm, with an outer diameter of 339.7mm. A liner can extend to the bottom of the emplacement zone to aid in retrievability. The liner has an outer diameter of 406.4mm and a thickness of 9.52mm. The standard drill bit used with a liner of this size has an outer diameter of 444.5mm. Sample calculations were performed for a two kilometer deep emplacement zone in a four kilometer deep hole for the conservative case of PWR fuel having a burnup of 60,000 MWd/kg, cooled ten years before emplacement.
(cont.) Tensile and buckling stresses were calculated, and found to be tolerable for a high grade of steel used in the drilling industry. In the thermal analysis, a maximum borehole wall temperature of 2400C is computed from available correlations and used to calculate a maximum canister centerline temperature of 3370C, or 3190C if the hole floods with water. Borehole repository construction costs were calculated to be on the rate of 50 $/kg spent fuel, which is competitive with Yucca Mountain construction costs. Recommendations for future work on the very deep borehole concept are suggested in the areas of thermal analysis, plugging, corrosion of the steel canisters, site selection, and repository economics.
by Christopher Ian Hoag.
S.M.
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Bonnett, Timothy Charles. "A systems view of the nuclear waste dilemma." Master's thesis, This resource online, 1991. http://scholar.lib.vt.edu/theses/available/etd-01202010-020205/.

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Kuo, Weng-Sheng. "Evaluation of deep drillholes for high level nuclear waste disposal." Thesis, Massachusetts Institute of Technology, 1991. http://hdl.handle.net/1721.1/45197.

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Sizer, Calvin Gregory. "Minor actinide waste disposal in deep geological boreholes." Thesis, Massachusetts Institute of Technology, 2006. http://hdl.handle.net/1721.1/41595.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2006.
Includes bibliographical references (leaves 63-65).
The purpose of this investigation was to evaluate a waste canister design suitable for the disposal of vitrified minor actinide waste in deep geological boreholes using conventional oil/gas/geothermal drilling technology. The nature of minor actinide waste was considered, paying particular attention to nuclides whose decay energy and half lives were of relative significance to the minor actinide waste as a whole. Thermal Analysis was performed based on a reference borehole design, by Ian C. Hoag. The strategy of the thermal analysis is aimed at finding peak temperatures within the configuration, paying particular attention to the heat transfer under deep geological conditions in the air gap between the canister and the borehole. A first order economic analysis was made to compare the designed canister emplacement costs to that of intact spent fuel. The results of this analysis show that three minor actinide nuclides dominate heat generation after ten years cooling: Cm-244, Am-241, and Am-243 account for 97.5% of minor actinide decay heat. These three nuclides plus Np-237 account for 99% of the minor actinide mass. The thermal analysis was based on an irretrievable canister design, consisting of a 5 meter long synroc waste form, with minor actinides loaded to 1% wt, an outer radius of 15.8 cm and inner annular radius of 8.5 cm. Filling the annulus with a vitrified technetium and iodine waste form was found to be feasible using a multi-stage emplacement process. This process would only be required for three of the fifty boreholes because technetium and iodine have low heat generations after 10 years cooling. The suggested borehole waste form has a maximum centerline temperature of 349C. The costs of drilling boreholes to meet the demand of 100,000MT of PWR waste are estimated to be 3.5% of the current nuclear waste fund, or about $9.6/kg of original spent fuel.
by Calvin Gregory Sizer.
S.B.
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Gunderson, Katie Marie. "Radiation damage in phosphates and silicates for nuclear waste disposal." Thesis, University of Cambridge, 2013. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.608095.

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Pascual, Christopher C. "Evaporation measurements from simulated nuclear waste storage tanks." Diss., Georgia Institute of Technology, 1996. http://hdl.handle.net/1853/18208.

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Bates, Ethan Allen. "Optimization of deep boreholes for disposal of high-level nuclear waste." Thesis, Massachusetts Institute of Technology, 2015. http://hdl.handle.net/1721.1/97968.

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Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2015.
Cataloged from PDF version of thesis.
Includes bibliographical references (pages 223-240).
This work advances the concept of deep borehole disposal (DBD), where spent nuclear fuel (SNF) is isolated at depths of several km in basement rock. Improvements to the engineered components of the DBD concept (e.g., plug, canister, and fill materials) are presented. Reference site parameters and models for radionuclide transport, dose, and cost are developed and coupled to optimize DBD design. A conservative and analytical representation of thermal expansion flow gives vertical velocities of fluids vs. time (and the results are compared against numerical models). When fluid breakthrough occurs rapidly, the chemical transport model is necessary to calculate radionuclide concentrations along the flow path to the surface. The model derived here incorporates conservative assumptions, including instantaneous dissolution of the SNF, high solubility, low sorption, no aquifer or isotopic dilution, and a host rock matrix that is saturated (at a steady state profile) for each radionuclide. For radionuclides that do not decay rapidly, sorb, or reach solubility limitations (e.g., 1-129), molecular diffusion in the host rock (transverse to the flow path) is the primary loss mechanism. The first design basis failure mode (DB 1) assumes the primary flow path is a 1.2 m diameter region with 100x higher permeability than the surrounding rock, while DB2 assumes a 0.1 mm diameter fracture. For the limiting design basis (DB 1), borehole repository design is constrained (via dose limits) by the areal loading of SNF (MTHM/km2 ), which increases linearly with disposal depth. In the final portion of the thesis, total costs (including drilling, site characterization, and emplacement) are minimized ($/kgHM) while borehole depth, disposal zone length, and borehole spacing are varied subject to the performance (maximum dose) constraint. Accounting for a large uncertainty in costs, the optimal design generally lies at the minimum specified disposal depth (assumed to be 1200 in), with disposal zone length of 800-1500 m and borehole spacing of 250-360 meters. Optimized costs range between $45 to $191/kgHM, largely depending on the assumed emplacement method and drilling cost. The best estimate (currently achievable), minimum cost is $134/kgHM, which corresponds to a disposal zone length of -900 meters and borehole spacing of 272 meters.
by Ethan Allen Bates.
Ph. D.
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Shaikh, Samina. "Effective thermal conductivity measurements relevant to deep borehole nuclear waste disposal." Thesis, Massachusetts Institute of Technology, 2007. http://hdl.handle.net/1721.1/41301.

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Thesis (S.M. and S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007.
Includes bibliographical references (leaves 106-107).
The objective of this work was to measure the effective thermal conductivity of a number of materials (particle beds, and fluids) proposed for use in and around canisters for disposal of high level nuclear waste in deep boreholes. This information is required to insure that waste temperatures will not exceed tolerable limits. Such experimental verification is essential because analytical models and empirical correlations can not accurately predict effective thermal conductivities for complex configurations of poorly characterized media, such as beds of irregular particles of mixed sizes. The experimental apparatus consisted of a 2.54 cm. diameter cylindrical heater (heated length = 0.5 m) , surrounded by a 5.0 cm inner diameter steel tube. Six pairs of thermocouples were located axially on the inside of the heater sheath, and in grooves on the air-fan-cooled outer tube. Test media were used to fill the annular gap, and the temperature drop across the gap measured at several power levels covering the range of heat fluxes expected on a waste canister soon after emplacement. Values of effective thermal conductivity were measured for air, water; particle beds of sand, SiC, graphite and aluminum; and an air gap subdivided by a thin metal sleeve insert. Results are compared to literature values and analytical models for conduction, convection and radiation. Agreement within a factor of 2 was common, and the results confirm the adequacy, and reduce the uncertainty of prior borehole system design calculations. All particle bed data fell between 0.3 and 0.5 W/moC, hence other attributes can determine usage.
by Samina Shaikh.
S.M.and S.B.
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Books on the topic "Nuclear disposal"

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Hare, Tony. Nuclear waste disposal. London: Gloucester Press, 1991.

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Holt, Mark. Civilian nuclear waste disposal. [Washington, D.C.]: Congressional Research Service, Library of Congress, 1999.

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Holt, Mark. Civilian nuclear waste disposal. [Washington, D.C.]: Congressional Research Service, Library of Congress, 2000.

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Holt, Mark. Civilian nuclear waste disposal. [Washington, D.C.]: Congressional Research Service, Library of Congress, 2001.

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Holt, Mark. Civilian nuclear waste disposal. [Washington, D.C.]: Congressional Research Service, Library of Congress, 2004.

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Holt, Mark. Civilian nuclear waste disposal. [Washington, D.C.]: Congressional Research Service, Library of Congress, 2001.

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Holt, Mark. Civilian nuclear waste disposal. [Washington, D.C.]: Congressional Research Service, Library of Congress, 2000.

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Holt, Mark. Civilian nuclear waste disposal. [Washington, D.C.]: Congressional Research Service, Library of Congress, 2001.

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Holt, Mark. Civilian nuclear waste disposal. [Washington, D.C.]: Congressional Research Service, Library of Congress, 2003.

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Holt, Mark. Civilian nuclear waste disposal. [Washington, D.C.]: Congressional Research Service, Library of Congress, 1992.

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Book chapters on the topic "Nuclear disposal"

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Eidemüller, Dirk. "Disposal." In Nuclear Power Explained, 241–87. Cham: Springer International Publishing, 2021. http://dx.doi.org/10.1007/978-3-030-72670-6_11.

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Jagger, John. "Nuclear Waste Disposal." In The Nuclear Lion, 133–57. Boston, MA: Springer US, 1991. http://dx.doi.org/10.1007/978-1-4899-2784-2_10.

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Cohen, Bernard L. "The Waste Disposal Risk." In Nuclear Energy, 299–311. Boston, MA: Springer US, 1985. http://dx.doi.org/10.1007/978-1-4684-4589-3_17.

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Fig, David. "Disposal and Contamination." In Challenges of Nuclear Waste Governance, 295–328. Wiesbaden: Springer Fachmedien Wiesbaden, 2018. http://dx.doi.org/10.1007/978-3-658-21441-8_13.

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Fentiman, Audeen W. "Radioactive Waste Management: Storage, Transport, Disposal." In Nuclear Energy, 269–82. New York, NY: Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4614-5716-9_10.

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Singer, Clifford, and William R. Roy. "Spent Fuel and Waste Disposal." In Nuclear Energy Encyclopedia, 151–57. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2011. http://dx.doi.org/10.1002/9781118043493.ch16.

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Niibori, Yuichi. "Radioactive Waste Disposal." In An Advanced Course in Nuclear Engineering, 153–73. Tokyo: Springer Japan, 2015. http://dx.doi.org/10.1007/978-4-431-55417-2_6.

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Fentiman, Audeen W. "Radioactive Waste Management: Storage, Transport, and Disposal." In Nuclear Energy, 241–50. New York, NY: Springer New York, 2018. http://dx.doi.org/10.1007/978-1-4939-6618-9_29.

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Saha, Gopal B. "Disposal of Radioactive Waste." In Radiation Safety in Nuclear Medicine, 143–48. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-16406-5_10.

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Scheer, Dirk, Holger Class, and Bernd Flemisch. "Nuclear Energy and Waste Disposal." In Subsurface Environmental Modelling Between Science and Policy, 179–92. Cham: Springer International Publishing, 2020. http://dx.doi.org/10.1007/978-3-030-51178-4_8.

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Conference papers on the topic "Nuclear disposal"

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Kristiansen, Håvard, and Bernt Sigve Aadnøy. "Borehole Disposal of Nuclear Waste." In SPE/IADC International Drilling Conference and Exhibition. SPE, 2021. http://dx.doi.org/10.2118/204117-ms.

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Abstract Approximately 370 000 tons of high-level radioactive waste exists. Some nations have mature projects for disposing of such waste in mined repositories hundreds of meters below ground. Emplacement in boreholes of greater depth could be a cost-efficient and fast alternative, particularly for nations with relatively small amounts of waste. A borehole repository could be developed via an iterative process, which would ultimately end with the completion of a comprehensive safety case and a fully operational disposal facility which would be sealed and decommissioned in a reliable manner. Each design should be adapted to the properties of the waste in question, site-specific geological conditions, and regulatory requirements. This variability causes designs and cost estimates to differ. Overall, borehole disposal of high-level radioactive waste is an opportunity for the drilling industry to expand its service portfolio in a way that is beneficial to the environment and the safety of current and future generations.
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PUSCH, ROLAND, JÖRN KASBOHM, THAO HOANG-MINH, LAN NGUYEN-THANH, and LAURENCE WARR. "DEEP DISPOSAL OF SPENT NUCLEAR FUEL." In WASTE MANAGEMENT 2018. Southampton UK: WIT Press, 2018. http://dx.doi.org/10.2495/wm180371.

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STANCATI, MICHAEL, and ALAN FRIEDLANDER. "Disposal modes for Mars transfer nuclear propulsion." In Conference on Advanced SEI Technologies. Reston, Virigina: American Institute of Aeronautics and Astronautics, 1991. http://dx.doi.org/10.2514/6.1991-3410.

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Tian, Lifang, Mingfen Wen, and Jing Chen. "Treatment and Disposal of the Radioactive Graphite Waste." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29985.

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A large number of nuclear reactors with graphite as moderator and reflector material are facing to be decommissioned now or later, and the radioactive graphite waste is a large part of the involved wastes. In addition, high temperature gas-cooled reactors being developed rapidly use a large quantity of graphite material (up to 95%) in the nuclear fuel elements, besides graphite material as their moderator and reflector material in the reactor cores. Therefore, it is very critical to manage these graphite wastes from the decommissioned and being decommissioned reactors. The part with low-level radioactive contamination that could not be reused now, may be disposed of as solid waste to reduce its volume, and the possibility of its being retrieved and reused in the future with advanced technology should be considered. The other graphite waste with high-level radioactive contamination requires much more consideration. Due to several factors, such as its large quantity, a lack of available disposal sites and public acceptance, it may not be disposed of directly in the repository any more. An option may be the transformation of the high-level radioactive graphite waste into low-level radioactive waste through physical and chemical processes. The current technologies involve, e.g., thermal treatment to release 36Cl, capture of the 14C from the gases of incineration of carbon material and decomposition of carbon dioxide into solid carbon. After these treatments the carbon material might be decontaminated and separated as low-level radioactive waste and a small amount of residual high-level waste could be disposed of ultimately. In order to achieve a sustainable development of graphite material, the maximum utility and the minimal disposal of radioactive graphite should be considered in the management of radioactive graphite waste. It is urgent to explore new technologies for decontaminating and recycling radioactive graphite.
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Coopersmith, Jonathan. "Nuclear Waste Disposal in Space: BEP’s Best Hope?" In BEAMED ENERGY PROPULSION: Fourth International Symposium on Beamed Energy Propulsion. AIP, 2006. http://dx.doi.org/10.1063/1.2203301.

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Beitz, James V. "A single material approach to nuclear waste disposal." In Plutonium futures-The science (Topical conference on Plutonium and actinides). AIP, 2000. http://dx.doi.org/10.1063/1.1292237.

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Stefanova, Ira G. "Disposal of Spent Sealed Sources." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4972.

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Novi Han Repository is the only existing repository in Bulgaria for the disposal of radioactive waste from nuclear applications in industry, medicine and research. The disposal vault for spent sealed sources is not designed for disposal of powerful 137Cs and 60Co sources. Long-lived waste from nuclear applications are also not allowed for disposal at Novi Han Repository. As an operator of Novi Han Repository the Institute for Nuclear Research and Nuclear Energy initiated a program, for assessment of the possible utilization of deep shaft Gabra for disposal of such waste. The results of the preliminary study are discussed.
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Reimus, Paul W., and William L. Kuhn. "Simulation used to qualify nuclear waste glass for disposal." In the 19th conference. New York, New York, USA: ACM Press, 1987. http://dx.doi.org/10.1145/318371.318721.

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Graf, Reinhold, Wolfgang Filbert, Klaus-Ju¨rgen Brammer, and Wilhelm Bollingerfehr. "Disposal of Spent Fuel From German Nuclear Power Plants." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16028.

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The “direct disposal of spent fuel” as a part of the current German reference concept was developed as an alternative to spent fuel reprocessing and vitrified HLW disposal. The technical facilities necessary for the implementation of this part of the reference concept, the so called POLLUX® concept, i.e. interim storage buildings for casks containing spent fuel, a pilot conditioning facility, and a special cask “POLLUX” for final disposal have been built. With view to a geological salt formation all handling procedures for the direct disposal of spent fuel were tested aboveground in full-scale test facilities. To optimise the reference concept, all operational steps have been reviewed for possible improvements. The two additional concepts for the direct disposal of SF are the BSK 3 concept and the DIREGT concept. Both concepts rely on borehole emplacement technology, vertical boreholes for the BSK 3 concept und horizontal boreholes for the DIREGT concept. Supported by the EU and the German Federal Ministry of Economics and Technology (BMWi), DBE TECHNOLOGY built an aboveground full-scale test facility to simulate all relevant handling procedures for the BSK 3 disposal concept. GNS (Company for Nuclear Service), representing the German utilities, provided the main components and its know-how concerning cask design and manufacturing. The test program was concluded recently after more than 1.000 emplacement operations had been performed successfully. The BSK 3 emplacement system in total comprises an emplacement device, a borehole lock, a transport cart, a transfer cask which will shuttle between the aboveground conditioning facility and the underground repository, and the BSK 3 canister itself, designed to contain the fuel rods of three PWR-fuel assemblies with a total of about 1.6 tHM. The BSK 3 concept simplifies the operation of the repository because the handling procedures and techniques can also be applied for the disposal of reprocessing residues. In addition to this, the feasibility of the direct disposal of transport and storage casks, the so-called “DIREGT concept”, is being investigated. The implementation of this concept would avoid the necessity to separate fuel rods from structural parts and to procure custom-made final disposal casks. All investigations and studies performed so far support the feasibility of direct disposal of spent fuel in multipurpose casks as today used for transport and storage. Both additional concepts, BSK 3 and DIREGT, are expected to simplify disposal processes and to reduce operational risk without any compromise in long-term radiological safety aspects.
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MCCOMBIE, CHARLES. "ROLE AND STATUS OF GEOLOGICAL DISPOSAL." In International Seminar on Nuclear War and Planetary Emergencies 36th Session. WORLD SCIENTIFIC, 2007. http://dx.doi.org/10.1142/9789812709233_0010.

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Reports on the topic "Nuclear disposal"

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F. Habashi. DOE SPENT NUCLEAR FUEL DISPOSAL CONTAINER. Office of Scientific and Technical Information (OSTI), June 1998. http://dx.doi.org/10.2172/883436.

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Leigh, Christi D., and Francis D. Hansen. Salt disposal of heat-generating nuclear waste. Office of Scientific and Technical Information (OSTI), January 2011. http://dx.doi.org/10.2172/1005078.

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Brady, Patrick Vane, Bill Walter Arnold, Susan Jeanne Altman, and Palmer Vaughn. Deep borehole disposal of nuclear waste summary. Office of Scientific and Technical Information (OSTI), September 2012. http://dx.doi.org/10.2172/1055644.

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Laverov, N. P., B. L. Omelianenko, and V. I. Velichkin. Geological aspects of the nuclear waste disposal problem. Office of Scientific and Technical Information (OSTI), June 1994. http://dx.doi.org/10.2172/91959.

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Bouton, Jr, and Edwin H. High-Level Nuclear Waste Disposal: Policy and Prognosis. Fort Belvoir, VA: Defense Technical Information Center, April 1992. http://dx.doi.org/10.21236/ada262251.

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Wilfinger, K. Ceramic package fabrication for YMP nuclear waste disposal. Office of Scientific and Technical Information (OSTI), August 1994. http://dx.doi.org/10.2172/67743.

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L.F. Pincock, W.D. Hintze, and J. Duguid. Analysis of DOE Spent Nuclear Fuels for Repository Disposal. Office of Scientific and Technical Information (OSTI), February 2006. http://dx.doi.org/10.2172/893932.

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N. E. Pettit. Uncanistered Spent Nuclear fuel Disposal Container System Description Document. Office of Scientific and Technical Information (OSTI), July 2001. http://dx.doi.org/10.2172/790342.

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N. E. Pettit. Naval Spent Nuclear Fuel disposal Container System Description Document. Office of Scientific and Technical Information (OSTI), July 2001. http://dx.doi.org/10.2172/790343.

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J.A. Ziegler. CLASSIFICATION OF THE MGR DOE SPENT NUCLEAR DISPOSAL CONTAINER. Office of Scientific and Technical Information (OSTI), August 1999. http://dx.doi.org/10.2172/860597.

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