Skip to main content
SpringerLink
Log in

Immobilization of High Level Nuclear Wastes: The Indian Scenario

  • Chapter
  • First Online:
On a Sustainable Future of the Earth's Natural Resources

Part of the book series: Springer Earth System Sciences ((SPRINGEREARTH))

Abstract

Nuclear power stands as an immediate and sustainable soluton for satisfying the emerging energy crisis in India. Successful execution of any national ‘nuclear power program’ is keyed to its effective ‘high level nuclear waste’ management strategy. Towards this, India has recently developed sodium-barium-borosilicate glass matrix to immobilize sulfate containing high level waste. Currently, efforts are underway to explore the possibilities of using the same matrix or its modified versions to condition nuclear wastes likely to be generated from ‘closed thorium fuel cycle’. Apart from conventionally used ‘hot wall induction furnace technology’, India has recently acquired expertise in operations of indegineously developed ‘Joule heated ceramic melter’ and ‘Cold crucible induction melter’ for development of suitable inert glass matrices.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Log in via an institution
Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 169.00
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 219.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info
Hardcover Book
USD 219.99
Price excludes VAT (USA)
  • Durable hardcover edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

References

  • Anantharaman K (2007) Role of nuclear power in the Indian Energy Scenario. Gond Geol Mag 9:141–148

    Google Scholar 

  • Ando Y, Nishihara K, Takano H (2000) Estimation of spent fuel compositions from light water reactors. J Nucl Sci Tech 37:924–933

    Article  Google Scholar 

  • Banerjee K, Raj K, Wattal PK (2011) Process technology for vitrification of high-level radioactive liquid waste. In: Proceedings of international conference on peaceful uses of atomic energy −2009, vol 2. Nuclear Fuel Cycle, Vigyan Bhavan, 29 Sept–1 Oct 2009, pp 489–495

    Google Scholar 

  • Blasewitz AG, Richardson GL, McElroy JL, Mendel JE, Schneider KJ (1973) Management of radioactive wastes from fuel reprocessing. In: Organization for economic cooperation and development (ed), pp 615–654

    Google Scholar 

  • Dey PK, Bansal NK (2006) Spent fuel reprocessing; A vital link in Indian nuclear power program. Nucl Eng Des 236:723–729

    Article  Google Scholar 

  • Dey PK, Wattal PK (2011) Back-end of fuel cycle. In: Proceedings of international conference on peaceful uses of atomic energy −2009, vol 2. Nuclear Fuel Cycle, Vigyan Bhavan, 29 Sept–1 Oct 2009, pp 343–349

    Google Scholar 

  • Dey PK, Gupta AK, Achuthan PV, Kaushik CP, Yalmali V (2011) Thorium utilization – back-end challenges. In: Proceedings of international conference on peaceful uses of atomic energy −2009, vol 2. Nuclear Fuel Cycle, Vigyan Bhavan, 29 Sept–1 Oct 2009, pp 350–357

    Google Scholar 

  • Donald IW, Metcalfe BL, Taylor RNJ (1997) The immobilization of high level radioactive wastes using ceramics and glasses. J Mater Sci 32:851–887

    Article  Google Scholar 

  • Ewing RC (1979) Natural glasses: analogues for radioactive waste forms. In: McCarthy GJ (ed) Scientific basis for nuclear waste management, vol 1. Plenum, New York, pp 57–68

    Chapter  Google Scholar 

  • Grover V, Sengupta P, Bhanumurthy K, Tyagi AK (2006) Electron Probe Microanalysis (EPMA) investigations in the CeO2-ThO2-ZrO2 system. J Nucl Mater 350:169–172

    Article  Google Scholar 

  • Grover V, Sengupta P, Tyagi AK (2007) Sub-solidus phase relations in CeO2-YSZ and ThO2-YSZ systems: XRD, high-temperature XRD and EPMA studies. Material Sci Eng B138:246–250

    Article  Google Scholar 

  • Grover V, Banerji A, Sengupta P, Tyagi AK (2008) Raman, XRD and microscopic investigations on CeO2-Lu2O3 and CeO2-Sc2O3 systems: a sub-solidus phase evolution study. J Solid State Chem 181:1930–1935

    Article  Google Scholar 

  • Grover V, Cavan SV, Sengupta P, Tyagi AK (2010) CeO2-YO1.5-NdO1.5 system: an extensive phase relation study. J Eur Ceramic Soc 30:3137–3143

    Article  Google Scholar 

  • Haaker RF, Ewing RC (1981) Naturally occurring crystalline phases: analogues for radioactive waste forms, Pacific Northwest Lab. PNL – 3505/UC-70, Richland, Washington

    Google Scholar 

  • Hejzlar P, Driscoll MJ, Todreas NE (2000)Impact of fuel choices on spent fuel characteristics for once through heavy metal cooled reactors. In: Proceedings of committee meeting (TCM) on “core physics and engineering aspects of emerging nuclear energy systems for energy generation and transmutation” held in Argonne, Illinois, USA, 28 Nov–1 Dec 2000. IAEA, Vienna, IAEA-TECDOC- 1356, pp 168–185

    Google Scholar 

  • Hench LL, Clark DE, Campbell J (1984) High level waste immobilization forms. Nucl Chem Waste Manag 5:149–173

    Article  Google Scholar 

  • International Atomic Energy Agency (1992) Design and operation of high level waste vitrification and storage facilities, Technical Reports Series No. 339:50

    Google Scholar 

  • International Atomic Energy Agency (2001) Monitoring of geological repositories for high level waste, IAEA-TECDOC-1208:25

    Google Scholar 

  • International Atomic Energy Agency (2005) Status and trends in spent fuel reprocessing, IAEA-TECDOC-1467:101

    Google Scholar 

  • International Atomic Energy Agency (2007) Spent fuel and high level waste: chemical durability and performance under simulated repository conditions, IAEA-TECDOC-1563:29

    Google Scholar 

  • Jahagirdar PB, Wattal PK (1998) Vitrification of sulphate bearing high level wastes in borosilicate matrix. Waste Manage 18:265–273

    Article  Google Scholar 

  • Kain V, Sengupta P, De PK, Banerjee S (2005) Case reviews on the effect of microstructure on the corrosion behavior of austenitic alloys for processing and storage of nuclear waste. Metal Mater Transact 36A:1075–1084

    Article  Google Scholar 

  • Kaushik CP, Mishra RK, Sengupta P, Kumar A, Das D, Kale GB, Raj K (2006) Barium borosilicate glass- a potential matrix for immobilization of sulfate bearing high level radioactive liquid waste. J Nucl Mater 358:129–138

    Article  Google Scholar 

  • Kutty TRG, Kulkarni RV, Sengupta P, Khan KB, Bhanumurthy K, Sengupta AK, Panakkal JP, Kumar A, Kamath HS (2008a) Development of CAP Process for fabrication of ThO2-UO2 fuels Part II: characterization and property evaluation. J Nucl Mater 373:309–318

    Article  Google Scholar 

  • Kutty TRG, Nair MR, Sengupta P, Basak U, Kumar A, Kamath HS (2008b) Characterization of (Th-U)O2 fuel pellets made by impregnation technique. J Nucl Mater 374:9–19

    Article  Google Scholar 

  • Lee WE, Ojovan MI, Stennett MC (2006) Immobilization of radioactive waste in glasses, glass composite materials and ceramics. Adv App Ceram 105:3–12

    Article  Google Scholar 

  • Mishra RK, Sengupta P, Kaushik CP, Tyagi AK, Kale GB, Raj K (2007) Studies on immobilization of thorium in barium borosilicate glass. J Nucl Mater 360:143–150

    Article  Google Scholar 

  • Mishra RK, Sudarsan V, Sengupta P, Vatsa RK, Tyagi AK, Kaushik CP, Das D, Raj K (2008) Role of sulphate in structural modifications of sodium barium borosilicate glasses developed for nuclear waste immobilization. J Am Ceram Soc 91:3903–3907

    Article  Google Scholar 

  • Ojovan MI, Lee WE (2005) An introduction to nuclear waste immobilization. Elsevier, The Netherlands

    Google Scholar 

  • Ojovan MI, Lee WE (2007) New developments in glassy nuclear wasteforms. Nova Science Pub Inc, New York

    Google Scholar 

  • Organisation for Economic Co-operation and Development (1999) Confidence in the long term safety of deep geological repositories. NEA/OECD, Paris

    Google Scholar 

  • Raj K, Kaushik CP (2009) Glass matrices for vitrification of radioactive waste – an update on R & D efforts, IOP conference series. Mater Sci Eng 2:1–6

    Google Scholar 

  • Raj K, Prasad KK, Bansal NK (2006) Radioactive waste management practices in India. Nucl Eng Des 236:914–930

    Article  Google Scholar 

  • Rempe NT (2008) Deep geological repositories. The Geological Society of America, USA

    Google Scholar 

  • Ringwood AE (1978) Safe disposal of high level nuclear reactor wastes: a new strategy. Australian National University Press, Canberra

    Google Scholar 

  • Ringwood AE (1985) Disposal of high level nuclear wastes: a geological perspective. Min Mag 49:159–176

    Article  Google Scholar 

  • Ringwood AE, Kesson SE, Ware NG, Hibberson W, Major A (1979) Immobilization of high level nuclear reactor wastes in SYNROC. Nature 278:219–223

    Article  Google Scholar 

  • Roy R (1975) Ceramic science of nuclear waste fixation. Am Ceram Soc Bull 54:459

    Google Scholar 

  • Roy R (1979) Science underlying radioactive waste management: status and needs. In: McCarthy GJ (ed) Scientific basis for nuclear waste management, vol 1. Plenum, New York, pp 1–20

    Chapter  Google Scholar 

  • Sengupta P (2011) Interaction study between nuclear waste glass melt and ceramic melter bellow liner materials. J Nucl Mater 411:181–184

    Article  Google Scholar 

  • Sengupta P, Gawde PS, Bhanumurthy K, Kale GB (2004) Diffusion reaction between Zircaloy 2 and Thoria. J Nucl Mater 325:180–187

    Article  Google Scholar 

  • Sengupta P, Mittra J, Kale GB (2006) Interaction between borosilicate melt and Inconel. J Nucl Mater 350:66–73

    Article  Google Scholar 

  • Sengupta P, Kaushik CP, Mishra RK, Kale GB (2007) Microstructural characterization and role of glassy layer developed on Inconel 690 during a nuclear high-level waste vitrification process. J Am Ceram Soc 90:3057–3062

    Article  Google Scholar 

  • Sengupta P, Soudamini N, Kaushik CP, Jagannath Mishra RK, Kale GB, Raj K, Das D, Sharma BP (2008) Corrosion of alloy 690 process pot by sulfate containing high level radioactive waste at feed stage. J Nucl Mater 374:185–191

    Article  Google Scholar 

  • Sengupta P, Kaushik CP, Kale GB, Das D, Raj K, Sharma BP (2009) Evaluation of Alloy 690 process pot at the contact with borosilicate melt pool during vitrification of high level nuclear waste. J Nucl Mater 392:379–385

    Article  Google Scholar 

  • Sengupta P, Rogalla D, Becker HW, Dey GK, Chakraborty S (2011a) Development of graded Ni-YSZ composite coating on Alloy 690 by Pulsed Laser Deposition technique to reduce hazardous metallic nuclear waste inventory. J Hazard Mater 192:208–221

    Google Scholar 

  • Sengupta P, Fanara S, Chakraborty S (2011b) Preliminary study on calcium aluminosilicate glass as a potential host matrix for radioactive 90Sr – an approach based on natural analogue study. J Hazard Mater 190:229–239

    Article  Google Scholar 

  • Srivastava A, Chandra S, Grover RB (2007) Energy indicators for sustainable energy and electricity growth in India. Gond Geol Mag 9:251–260

    Google Scholar 

  • Sugilal G (2008) Experimental analysis of the performance of cold crucible induction glass melter. Appl Therm Eng 28:1952–1961

    Article  Google Scholar 

  • Vaswani GA, Jahgirdar PB, Rastogi RC, Sundar Rajan NS (1979) Development of suitable radioactive waste product with low formation temperature and improved leach resistance – a practical approach, Internal report BARC-1028. Bhabha Atomic Research Centre, Mumbai

    Google Scholar 

  • Yalmali VS, Deshingkar DS, Wattal PK, Bharadwaj SR (2007) Preparation and characterization of vitrified glass matrix for high level waste form MOX fuel reprocessing. J Non-Cryst Sol 353:4647–4653

    Article  Google Scholar 

  • Yeotikar RG, Kaushik CP, Shah JG (2011) Matrices for immobilization of HLW and their characterization. In: Proceedings of international conference on peaceful uses of atomic energy −2009, vol 2. Nuclear Fuel Cycle, Vigyan Bhavan, 29 Sept–1 Oct 2009, pp 475–482

    Google Scholar 

Download references

Acknowledgements

Pranesh Sengupta is grateful to the organizers of Alexander von Humboldt Foundation (Germany) Kolleg ‘Earth-Future (2011)’, held at Periyar University, Salem (India) from 7th to 9th September, 2011, for inviting the contribution.

Author information

Authors and Affiliations

  1. Materials Science Division, Bhabha Atomic Research Centre, Mumbai, 400 085, India

    Pranesh Sengupta

  2. Waste Management Division, Bhabha Atomic Research Centre, Mumbai, 400 085, India

    C. P. Kaushik & G. K. Dey

Authors
  1. Pranesh Sengupta
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. C. P. Kaushik
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. G. K. Dey
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Pranesh Sengupta .

Editor information

Editors and Affiliations

  1. , Department of Geology, Periyar University, Salem, 636011, India

    Mu. Ramkumar

Rights and permissions

Reprints and permissions

Copyright information

© 2013 Springer-Verlag Berlin Heidelberg

About this chapter

Cite this chapter

Sengupta, P., Kaushik, C.P., Dey, G.K. (2013). Immobilization of High Level Nuclear Wastes: The Indian Scenario. In: Ramkumar, M. (eds) On a Sustainable Future of the Earth's Natural Resources. Springer Earth System Sciences. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-32917-3_2

Download citation

Publish with us

Policies and ethics

Search

Navigation