Physics design of experimental metal fuelled fast reactor cores for full scale demonstration

Devan, K.; Bachchan, Abhitab; Riyas, A.; Sathiyasheela, T.; Mohanakrishnan, P.; Chetal, S.C.

doi:10.1016/j.nucengdes.2011.05.016

Cited by 28 publications

(6 citation statements)

References 13 publications

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“…This excludes the possibility that representative tests of full-size metal fuel elements filled with sodium will be performed in the BN-cores consisted of ceramic fuel elements filled with helium. This circumstance had an influece upon decision of Indian specialists to design and construct the testing reactor MFTR of 320MW in thermal power for testing full-size metal fuel elements as a part of full-size FAs which are typical of commercial power-generating BN-reactors to be constructed [2].…”

Section: The Elements Under Development Must Meet the Principle Of Inmentioning

confidence: 99%

Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type

Golovchenko¹

2013

IJEPE

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The article deals with the initial requirements for metal fuel elements and commercial reactors using this type of elements: high smear density of fuel, high technological effectiveness of fuel, fuel column and fuel elements; interchangeability of metal fuel elements and oxide fuel elements; achievement of fuel breeding ratio of the core BRC ~1.0; prolongation of refuelling cycle up to Tc~11 months. The article presents content and results of examinations of radiation-thermal effects in U fuel column elements and UPu fuel column elements: irradiation of breeding and fuel elements in the BOR-60 and BN-350 reactors; research of macroeffects of radiation growth, radiation swelling, fuel-cladding chemical interaction. Applicability of the obtained results for developing advanced BN-reactors with heterogeneous cores of various types was discussed: with by FA heterogenization of the core (BFAH); intra FA heterogenization of the core (IFAH); intra fuel element heterogenization (IFEH).

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Section: The Elements Under Development Must Meet the Principle Of Inmentioning

confidence: 99%

Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type

Golovchenko¹

2013

IJEPE

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“…Future of the expanded nuclear power industry of Fast Breeder Reactors (FBRs) depends critically on the choice of fuel cycle, especially a fuel type which has the potential for high breeding so that doubling time is shorter. Therefore the development of metal fuel reactors has been recognized (Baldev Raj et al, 2005;Chetal, 2009) and metal FBR cores having various sizes have been designed to study their neutronics characteristics (Devan et al, 2011;Riyas and Mohanakrishnan, 2008). Harder neutron spectrum due to the absence of lighter atoms in metal reactors increases breeding ratio.…”

Section: Introductionmentioning

confidence: 99%

An investigation on Unprotected Loss of Flow Accident in Th–Pu metal fuelled 500 MWe fast reactor

Stephen

Sathiyasheela

Paul

et al. 2015

Annals of Nuclear Energy

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“…The advantages of metal fuelled FBRs are well documented and reported elsewhere. [1][2][3][4] Uranium-based alloys have been proposed as the fuel material for fast breeder reactors. 2,3 Pure uranium has three allotropic forms.…”

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confidence: 99%

“…[1][2][3][4] Uranium-based alloys have been proposed as the fuel material for fast breeder reactors. 2,3 Pure uranium has three allotropic forms. At high temperatures (776 °C-1132 °C), uranium exhibits bodycentered cubic (BCC) structure, the γ (gamma) phase.…”

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confidence: 99%

“…6,[8][9][10][11] U-Zr and U-Pu-Zr alloys are the leading candidates for Indian fast breeder reactors. 2,3,12 U-Nb and U-Nb-Zr alloys are also considered attractive candidates for FBRs because of many favourable properties like (i) high density and solidus temperature, (ii) high thermal conductivity, (iii) good compatibility with clad materials, (iv) resistance towards corrosion and (v) enhanced ductility compared to pure uranium metal. 9,13-15 U-7.5Nb-2.5Zr (Mulberry alloy), the most studied ternary alloy, has a good compromise of all the aforementioned properties.…”

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confidence: 99%

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Preparation of U-Nb alloy from oxide precursors by direct oxide electrochemical reduction method

Khan¹,

Mukherjee²,

Kumaresan³

2022

J. Electrochem. Soc.

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The aim of the present study was to prepare U-7 wt.% Nb alloy by the direct oxide electrochemical reduction method. The alloy was prepared from the mixed oxide precursors namely, UO2 and Nb2O5. When the precursors were sintered in a reducing atmosphere of Ar-8 vol.% H2, Nb2O5 was converted into NbO2. Subsequently, the mixed oxide pellet (UO2-NbO2) was reduced by the lithium metal, electrochemically generated from a molten LiCl-1 wt.% Li2O bath at 700°C. The electro-lithiothermic reduction was performed by constant current electrolysis mode with a mixed oxide pellet as the cathode and platinum as the anode. The reduction pathways of the individual oxides and the mixture were established using cyclic voltammetry and potentiostatic electrolysis techniques. The reduced alloy was characterized by X-ray diffraction and scanning electron microscopy-energy dispersive spectroscopy (SEM-EDS). These results confirmed the formation of U-Nb alloy. The composition of the alloy was determined by EDS, energy-dispersive X-ray fluorescence and chemical analysis.

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Physics design of experimental metal fuelled fast reactor cores for full scale demonstration

Cited by 28 publications

References 13 publications

Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type

Oxide-Metal Core Is Possible Transition to the Metal Fuel Core for Fast Reactors of the BN-Type

An investigation on Unprotected Loss of Flow Accident in Th–Pu metal fuelled 500 MWe fast reactor

Preparation of U-Nb alloy from oxide precursors by direct oxide electrochemical reduction method

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