Radioactive waste management practices in India

Raj, Kanwar; Prasad, K. Krishna; Bansal, Nikita

doi:10.1016/j.nucengdes.2005.09.036

Cited by 159 publications

(40 citation statements)

References 4 publications

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“…A typical Indian 500 MWe FBR has 181 fuel subassemblies arranged in a triangular array and a fuel subassembly contains 217 helium bonded pins each of 6.6 mm outside diameter (Raj et al, 2006). The neutron flux levels in FBRs are about two orders of magnitude higher (~10 15 n/ cm 2 s -1 ) than thermal reactors.…”

Section: Fast Reactors -Materials Aspectsmentioning

confidence: 99%

“…The matrix should remain stable for several thousands of years (Joseph et al, 2011). Borosilicates (Raj et al, 2006).…”

Section: Materials For Fuel Cycle: Present Status and Short-term Stramentioning

confidence: 99%

“…Fast reactor fuels are normally reprocessed by conventional PUREX process and coatings and surface modification have been attempted for enhancing the performance and service life of components made of Type 304L SS and titanium (Raj et al, 2006).…”

mentioning

confidence: 99%

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Materials Science & Technology: Research and Challenges in Nuclear Fission Power

Raja¹

2015

Proceedings of the Indian National Science Academy

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The performance and integrity of structural and functional materials are key issues in the safety and competitiveness of current and future nuclear fission reactors being developed for sustainable nuclear energy applications. The challenges towards development of nuclear structural materials arise due to the demanding hostile environments with respect to radiation, temperature, stress, etc., and requirements of total reliability and high performance over the long service life (say 60 years). A successful materials science research programme in nuclear industry has to take into account these challenges to improve the performance of materials and components in the emerging scenario of extending life of existing plants and realizing advanced reactors. In this study, material challenges associated with water reactors and fast breeder reactors (FBR) with focus on short-term and long-term strategies for materials development are considered. The materials in the existing and proposed future nuclear fission reactors are summarized along with a description of major material degradation mechanisms in different environments. The priority in the nuclear industry is to extend the life of reactors with robust safety features and sufficient cost-effectiveness, beyond forty to sixty years and from sixty to even one hundred years. The importance of modelling and developing predictive tools to estimate materials behaviour for effective computing of lifetime of nuclear reactor components is fast developing to cut down cost and time and also to enhance safety and confidence in existing and new systems. The future FBR technology relies heavily on advanced waste management and effective proliferation resistance. We review advanced reactor concepts of Generation IV forum and the new materials and technologies. Nuclear energy is not the right option for every country. Careful examination of the energy basket and commitment over a long period with effective mechanisms of safety governance is the key to make a decision to harness large amounts of nuclear energy. China, France, India, Russia, USA,UK, etc. are extremely committed to use large amounts of nuclear energy. Japan after the Fukushima accident, faces a challenge of public acceptance though the country has deep and rich expertise in nuclear technology and it is advantageous to produce low carbon power, on a sustained competitive basis from nuclear energy.

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Section: Fast Reactors -Materials Aspectsmentioning

confidence: 99%

“…The matrix should remain stable for several thousands of years (Joseph et al, 2011). Borosilicates (Raj et al, 2006).…”

Section: Materials For Fuel Cycle: Present Status and Short-term Stramentioning

confidence: 99%

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Materials Science & Technology: Research and Challenges in Nuclear Fission Power

Raja¹

2015

Proceedings of the Indian National Science Academy

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“…Thereby, it seems that in terms of radiological point of view, 137 Cs is the most important radionuclide produced in a nuclear process. 90 Sr radionuclide has long physical (t 1/2 : 28.60 years) and biological half-life and dispersion of 90 Sr to the environment causes damages to human body by incorporation into bones and teeth due to its high energetic beta particles (E β : 546 keV) [3][4][5][6][7][8].…”

Section: Introductionmentioning

confidence: 99%

New Solidification Materials in Nuclear Waste Management

Yanikomer¹,

Asal²,

Haciyakupoglu³

et al. 2016

IJET

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Abstract-One of the major worldwide environmental issue is the long-term storage or disposal of nuclear waste. Research in solidification materials for long-term storage of high-level nuclear wastes in nuclear industry has started as an imperative need. During the last decade, new solidification materials have been developed for immobilization of actinides and fission products for geological disposal. The materials used for immobilization generally have relatively complex compositions. The structure of these materials investigates using diffraction and spectroscopic methods. Most of the interest has focused on their chemical durabilities and capacity of waste loading. Their physical and chemical properties should not be degraded by -decay event irradiation from the incorporated actinides. The development of new materials either for storage or for disposal for a long time is still required. In this article, recent developments in the use of solidification materials for the immobilization of high level of nuclear wastes have been reviewed. The comparison of properties of solidification materials is summarized with several applications in connection with experience and technological needs in literature.

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“…Various activities in nuclear installations, all over the world, generate different varieties of waste streams other than High Level Liquid Waste (HLLW) produced in spent fuel reprocessing [1,2]. Significant amounts of actinides with diverse ionic compositions are present in these waste streams, which must be removed owing to their extremely hazardous characteristics.…”

Section: Introductionmentioning

confidence: 99%

Simultaneous separation and purification of plutonium and americium from aqueous nitrate solutions using extractant impregnated macroporous polymeric beads

Pathak

Tripathi

Singh

et al. 2015

J Radioanal Nucl Chem

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The removal of Pu(IV) and Am(III) ions from aqueous nitrate solutions was studied using indigenously synthesized Extractant Impregnated Macroporous Polymeric Beads (EIMPBs). These beads exhibited almost quantitative sorption of Pu(IV) at acid strength of [2 M HNO 3 while that of Am(III) at pH 3. Langmuir sorption model was found suitable, with the sorption capacity of EIMPBs for Pu(IV) and Am(III) as 2.13 and 2.64 mg g -1 respectively. Its performance remained unchanged until seven cycles of extraction and stripping using 0.1 M oxalic acid. A flow sheet for Purification of Pu(IV)/Am(III) from its mixture is proposed.

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Radioactive waste management practices in India

Cited by 159 publications

References 4 publications

Materials Science & Technology: Research and Challenges in Nuclear Fission Power

Materials Science & Technology: Research and Challenges in Nuclear Fission Power

New Solidification Materials in Nuclear Waste Management

Simultaneous separation and purification of plutonium and americium from aqueous nitrate solutions using extractant impregnated macroporous polymeric beads

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