Current Status of Fast Reactors and Future Plans in India

Chetal, S.C.; Chellapandi, P.; Puthiyavinayagam, P.; Raghupathy, S.; Balasubramaniyan, V.; Selvaraj, P.; Mohanakrishnan, P.; Raj, Baldev

doi:10.1016/j.egypro.2011.06.009

Cited by 39 publications

(4 citation statements)

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“…Addition of NMFPs and U might have increased the quantity of the intermetallic phases (as evidenced from the number and intensity of peaks corresponding to the intermetallics shown in Figs. [2][3][4][5], thereby increasing the hardness values. Fig.…”

Section: Hardness Measurementmentioning

confidence: 97%

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Influence of noble metal fission products and uranium on the microstructure and corrosion behaviour of D9 stainless steel–zirconium metal waste form alloy

Bairi

Mallika

Mudali

2014

Journal of Nuclear Materials

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Section: Hardness Measurementmentioning

confidence: 97%

“…The wastes generated from the reprocessing of spent nuclear fuel needs special attention as it is hazardous and possesses high radioactivity [1][2][3]. Reprocessing of the spent metallic fuel using pyrochemical process provides several advantages [4,5].…”

Section: Introductionmentioning

confidence: 99%

Influence of noble metal fission products and uranium on the microstructure and corrosion behaviour of D9 stainless steel–zirconium metal waste form alloy

Bairi

Mallika

Mudali

2014

Journal of Nuclear Materials

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“…In addition, the use of metallic fuel along with the Pyro-process recycling could be more economical than Purex reprocessing based recycling. In view of this, the long term Indian fast reactor programme will be based on metallic fuels [3]. U-Pu-Zr ternary alloy fuel, due to its higher solidus temperature and higher eutectic with T91 clad, it is one of the most suitable options for development of high breeding fuels for fast breeder reactors.…”

Section: Introductionmentioning

confidence: 99%

Studies on U-Zr and U-Pu-Zr alloys for determination of Cl and F using pyrohydrolysis

Mishra¹,

Sali

Shah³

et al. 2014

Radiochimica Acta

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Pyrohydrolysis method was studied for the separation of Cl and F from U-Zr and U-Pu-Zr alloy nuclear fuels and determination by ion chromatography. A detailed study was performed on pyrohydrolysed products of U-Zr alloy, obtained on heating in moist argon and oxygen atmospheres using X-ray powder diffraction (XRD) and thermogravimtric methods. Using oxygen as the carrier gas pyrohydrolysis performed at 900 ∘ C was complete within 30 min. It was found that, moist oxygen as carrier gas only could open the matrix completely within stipulated time.This was attributed to the formation of -U 3 O 8 , which was not possible in moist argon heating for 30 min. The pyrohydrolysis in moist Ar required 60-90 min for complete removal of halides. The method was then successfully extrapolated to U-Pu-Zr alloys. The results showed recovery up to 90% or above for the optimized conditions.

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“…Summary of SMR technology[18][19][20][29][30][31][32][33][34][35][36][37][38][39] [40][41][42][43][44][45][46][47][48][49][50] …”

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Computational fluid dynamics of advanced nuclear reactor cores and its contribution to safety analysis

Rowinski¹

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Analytical methods and Computational Fluid Dynamics (CFD) examined the safety and performance of advanced nuclear reactors. Thermal and pressure drop evaluations of an innovative annular fuel in the European lead-cooled System ELSY fast reactor were conducted. Annular fuel has superior cooling capacity, and for a square fuel lattice, the pressure drop can be lower than the reference value for standard solid fuel. Consequently, when annular fuel rods replace solid fuel rods of the same dimensions the power rating is upgraded. While the hexagonal lattice cools more effectively, the pressure drop is higher than the standard fuel assembly and incompatible with power augmentation. Numerical investigations of supercritical flow of both carbon dioxide and water in a vertical tube under non-uniform heat flux applied at the wall demonstrated that current correlations for the Heat Transfer Coefficient (HTC) at low enthalpy values are accurate to ±15%. At high enthalpy, only the general trend is replicated due to large property value differences near the wall and in the bulk flow. In these circumstances, the thermal conductivity, specific heat, density and viscosity are 5-8 times lower after the transition from sub-to super-critical conditions. Moreover, the efficiency of different HTC correlation models is coolant dependant, e.g. the Swenson* formula proves superior for carbon dioxide, whereas the Ornatsky model** provides better agreement with water, where a lower maximum wall temperature was obtained when a non-uniform heat flux was applied, as compared to the reference case of uniform heat flux. For supercritical water flow inside a 2  2 fuel rod bundle, non-uniform heat flux increases wall temperature beyond the reference uniform flux. Also, wall temperature peaks occur only at the gaps between the fuel rods.

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Current Status of Fast Reactors and Future Plans in India

Cited by 39 publications

References 0 publications

Influence of noble metal fission products and uranium on the microstructure and corrosion behaviour of D9 stainless steel–zirconium metal waste form alloy

Influence of noble metal fission products and uranium on the microstructure and corrosion behaviour of D9 stainless steel–zirconium metal waste form alloy

Studies on U-Zr and U-Pu-Zr alloys for determination of Cl and F using pyrohydrolysis

Computational fluid dynamics of advanced nuclear reactor cores and its contribution to safety analysis

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