Abstract
A reference Geological Disposal System (GDS) for high level long lived heat emitting radioactive waste with dimension 20–10–6.25 m has been evaluated for time dependent heat field distribution, stress build up and possibility of micro-fracturing. The GDS comprises of three cylindrical heat sources (0.30 m diameter and 2 m length) mimicking radioactive waste loaded canisters emplaced within Jalore granite (JG) with barrier layers of Barmer bentonite (BB) clays, from Rajasthan. The methodology adopted in the study includes thermo- mechanical characterization of the granites and clays, followed by finite difference method (FDM) based numerical analysis for time dependent buildup of thermal and mechanical stresses, evolution of temperature field and micro fracturing phenomena within the studied GDS. The study reveals that three heat sources (waste filled SS canisters) of 500 watt intensity with spacing of 2.5 m and clay granite (CG) ratio of 60:40 and 70:30 produces maximum temperature of 92.42 and 94.69 °C and total stress (thermal and mechanical) of 24.77 and 24.97 MPa respectively within the system. 3.32 and 3.31 mm maximum displacement observed in the GDS for 60:40 and 70:30 CG ratio respectively which is within design limit. Analysis further establishes that clay admixture having bentonite clay and granite ratio in the range of 70:30 and 60:40 is capable of smooth dissipation of heat thorough them with resultant maximum temperature of < 100 °C throughout the entire duration of the time periods analysed. Based on these results it is concluded that JG and BB clay in 60:40 and 70:30 ratio with waste canister spacing of 2.5 m have appropriate characteristics suitable for hosting geological disposal system for heat emitting high level waste canisters. The study marks first analysis of multi-canister geological disposal system in Indian context.
Similar content being viewed by others
References
Alexander, W.R., Reijonen, H.M. and McKinley, I.G. (2015) Natural analogues: studies of geological processes relevant to radioactive waste disposal in deep geological repositories. Swiss Jour. Geosci., v.108, pp.75–100.
Ali, S.D. and Kim, J. (2017) A numerical simulation of thermo-mechanical behavior of the intact rock in response to the borehole heater test. Ann. Nucl. Energy, v.101, pp.301–311.
Bajpai, R.K. (2004) Recent advances in the geological disposal of nuclear wastes worldwide and Indian scenario. Jour. Geol. Soc. India, v.63(3), pp.354–356.
Bajpai, R.K. (2008) Characterization of Natural Barrier of Deep Geological Repository for high Level Radioactive Wastes in India. Indian Nucl. Soc. Bull., v.5(4), pp.41–48.
Bernd Grambow (2016) Geological Disposal of Radioactive Waste in Clay. Elements, v. 12(4), pp.239–245.
Bhushan, S.K. (1984) Classification of Malani Igneous suite. Geol. Surv. India, v.12, pp.199–205.
Bhushan, S.K. and Chittora (2005) Proterozoic granitoids of Rajasthan, Jour. Geol. Soc. India, v.66, pp.741–763.
Chapman, N.C., Combie, Mc (2003) Principles and standards for the disposal of long-lived radioactive wastes. 1st Ed., Pergamon Press, London.
Chijimatsu, M., Jing, L., Millard, A., Nguyen, T.S., Rejeb, A., Rutqvist, J., Souley, M., Sugita, Y. (2003) Building confidence in the mathematical models by calibration with a THM field experiment. Coupled Thermo-Hydro-Mechanical-Chemical Processes in Geo-Systems- Fundamentals, Modelling, Experiments and Applications, v.2, pp.193–198.
Cho, W.J., Kwon, S., Park, J.H. (2008) KURT- a small-scale underground research laboratory for the research on a high-level waste disposal. Ann. Nucl. Energy, v.35, pp.132–140.
Choi, J.W., Ko, W.I., Kim, S.G. (1997) Reference spent fuel and its characteristics for the concept development of a deep geological disposal system, KAERI report, KAERI/TR-914/97.
Choi, J.W., Cho, D.K., Lee, Y., Choi, H.J., Lee, J.Y., (2006) Assessment of a pre-conceptual design of a spent PWR fuel disposal container. Jour. Nucl. Fuel. Cycle Waste Tech., v.4, pp.41–50.
Choi, J.W., Ko, W.I., Kang, C.H. (1999) Reference spent fuel and its characteristics for a deep geological repository concept development. Nucl. Eng. Tech., v.31, pp.23–38.
Dutt A., Saini M.S., Singh T.N., Verma A.K., Bajpai R.K. (2012) Analysis of thermo-hydrologic-mechanical impact of repository for high-level radioactive waste in clay host formation: an Indian reference disposal system. Environ. Earth Sci., v.66, pp.2327–2341.
Dixon, D., Chandler, N., Graham, J., Gray, M.N. (2002) Two large-scale sealing tests conducted at atomic energy of Canada’s underground research laboratory: the buffer-container experiment and the isothermal test. Can. Geotech. Jour., v.39, pp.503–518.
Eric Sonnenthal, A. Ito, Nicolas Spycher, Kawakami, S. (2005) Approaches to modelling coupled thermal, hydrological, and chemical processes in the Drift Scale Heater Test at Yucca Mountain. Internat. Jour. Rock Mech. Min. Sci., v.42, pp.698–719.
Gautam, P.K., Verma, A.K., Sharma, P. and Singh, T.N. (2018) Evolution of thermal damage threshold of Jalore granite. Rock Mech. Rock Eng., v.51, pp.2949–2956.
Gautam, P., Singh, S.P., Agarwal, A., Singh, T.N. (2022) Thermo mechanical characterization of two jalore granites with different grain sizes for India’s HLW disposal. Bull. Eng. Geol. Environ., v.81, pp.1–26.
Gens, A., Sánchez, M., Guimarães, L., Alonso, E.E., Lloret, A., Olivella, S., Villar, M.V., Huertas, F. (2009) A full scale in situ heating test for high level nuclear waste disposal. Observations, analysis and interpretation. Géotechnique, v.59, pp.377–399.
Gens, A. and Garcia–Molina, A.J. (1998) Analysis of a full scale in situ test simulating repository conditions. Int. Jour. Num. Anal. Meth. Geomech., v.22, pp.515–548.
Gens, A., Do, L., Guimaraes, N. (2002) Factors controlling rock–clay buffer interaction in a radioactive waste repository. Engg. Geol., v.64, pp.297–308.
Gens, A., Do, L., Guimaraes, N., Olivella, S. (2005) THMC coupling in partially saturated geomaterials. Revue euroṕeenne de ǵenie civil, v.9, pp.747–765.
Gin, S. (2013) An international initiative on long-term behavior of high-level nuclear waste glass. Materials Today, v.16, pp.243–248.
Goodman, M.A. and Cowin, S.C. (1972) A continuum theory for granular material. Archive for Rational Mechanics and Analysis, v.44, pp.249–266.
Guo, R.P. (2011) Thermo hydro mechanical modelling of the buffer/container experiment. Eng. Geol., 122, pp.303–315.
Gawin, D., Baggio, P. and Schrefler, B.A. (1995) Coupled heat, water and gas flow in deformable porous media. Internat. Jour. Num. Meth. Fluids, v.20, pp.969–987.
Hedin, A. and Olsson, O. (2016) Crystalline Rock as a Repository for Swedish Spent Nuclear Fuel. Elements, v.12, pp.247–252.
Hocking, G., Williams, J.R., Mustoe, G.G.W. (1990) Post-test assessment of simulations for insitu heater tests in basalt- Heater test description and rock mass properties. Internat. Jour. Rock. Mech. Min. Geomech, v.27, pp.143–159.
IAEA Geological disposal facilities for radioactive waste (2011), IAEA Safety Standards Series No. SSG-14, STI/PUB/1483.
ISRM, B.E.T. (1981) Suggested methods: rock characterization, testing and monitoring. ISRM Commission on Testing Methods, Pergamon, Oxford.
Kaushik, C.P. (2014) Indian program for vitrification of high level radioactive liquid waste. Procedia Materials Science, v.7, pp.6–22.
Kaushik, C.P. and Ravi, K.V. (2022) Closed fuel cycle for for sustainable growth of nuclear power program in Inida. BARC Newsletter, v.380, pp.9–13.
Laverov, N.P., Yudintsev, S.V., Kochkin, B.T., Malkovsky, V.I. (2016) The Russian Strategy of using Crystalline Rock as a Repository for Nuclear Waste. Elements, v.12, pp.253–256.
Kwon, S., Park, J. H., Choi, J. W., and Kang, C. H. (2003), Thermo-mechanical sensitivity analysis of repository design parameters using Korean geological conditions. KAERI report, KAERI/TR-2360/2003.
Maheshwar, S., Verma A.K., Singh, T.N., Bajpai, R.K. (2015) A Numerical Study of THM Interference between Two Nuclear Waste Canisters of a Deep Geological Repository. Internat. Jour. Earth Sci. Engg., v.8, pp.21–30.
Mohammed Alzamel, Mamadou Fall and Sada Haruna (2022) Swelling ability and behaviour of bentonite-based materials for deep repository engineered barrier systems: Influence of physical, chemical and thermal factors. Jour. Rock Mech. Geotech. Eng., v.14(3), pp. 689–702.
Park, B.Y., Bae, D.S., Kim, C.S., Kim, K.S., Ko, Y.K. and Jeon, S.W. (2001) Evaluation of the basic mechanical and thermal properties of deep crystalline rocks. KAERI report, KAERI/TR-1828/2001.
Peter N. Swift and Evaristo J. Bonano (2016) Geological Disposal of Nuclear Waste in Tuff: Yucca Mountain (USA). Elements, v.12, pp.247–252.
Pusch, R., Svemar, C., Kaernbraenslehantering, S. (2004) Geo development and comparison of repository concepts and recommendations for design and construction of future safe repositories. SKB Report, FIR1-CT-2000-20023.
Raj, K.K. Prasad, Bansal, N.K. (2006) Radioactive waste management practices in India. Nuclear Eng. Design, v.236, pp. 914–930.
Rao, S. M., Kachroo, T.A., Allam, M.M., Joshi, M.R. and Acharya, A. (2008) Geotechnical characterization of some Indian bentonites for their use as buffer material in geological repository. Proceedings of 12th International Conference of International Association for Computer Methods and Advances in Geomechanics, pp. 2106–2114.
Thilo von Berlepsch and Bernt Haverkamp (2016) Salt as a Host Rock for the Geological Repository for Nuclear Waste. Elements, v.12, pp.247–252.
Vance, E.R., Begg, B.D. and Gregg, D.J. (2017) Immobilization of high-level radioactive waste and used nuclear fuel for safe disposal in geological repository systems. Geological repository systems for safe disposal of spent nuclear fuels and radioactive waste, 2nd Ed., Woodhead Publishing, pp. 269–295.
Verma, A.K., Gautam, P., Singh, T.N., Bajpai, R.K., 2015, Discrete element modelling of conceptual deep geological repository for high-level nuclear waste disposal. Arabian Jour. Geosci., v.8, pp. 8027–8038.
Yeotikar, R. G. (2007) High level liquid radioactive waste, their characterization and quality assurance. Indian Assoc. Nucl. Chemists and Allied Scientists (IANCAS) Bull., v.6, pp.204–217.
Zhao, H. G., Shao, H., Kunz, H., Su, R. and Liu, Y. M. (2014) Numerical analysis of thermal process in the near field around vertical disposal of high-level radioactive waste. Jour. Rock Mech. Geotech. Eng., v.6, pp.55–60.
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Kumar, B., Bajpai, R.K. & Singh, T.N. Time Dependent Evolution of Heat and Stress Field in Granite-clay System Representing Geological Disposal Scheme for High Level Radioactive Wastes. J Geol Soc India 99, 941–950 (2023). https://doi.org/10.1007/s12594-023-2415-9
Received:
Accepted:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s12594-023-2415-9