The limited indigenous uranium resource coupled with the need of energy independence necessitated the Department of Atomic Energy (DAE) in India to opt for a three-stage nuclear power program comprising of PHWRs in Stage 1, FBRs in Stage 2 and Th-U233 based reactors in Stage 3, respectively to meet the energy needs of the growing Indian economy. Presently the country has stepped into the 2nd Stage. The transition from the Stage 1 to 2 was fruitful thanks to the 2-decade long R&D experience gained in Fast Reactor Fuel Reprocessing (FRFR). Closing the fast reactor fuel cycle through FRFR was inevitable for the success of the Indian Nuclear Power Program (INPP). The latest achievement by the center was the successful reprocessing of 100 GWd/t burnup mixed carbide fuel with 70% Pu, discharged from the Fast Breeder Test Reactor (FBTR) which is also located in the same center. The designs of the various equipments and process flow sheet had stemmed from the above experiences thereby increasing the confidence le...

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Fast Reactor Fuel Reprocessing Technology in India

The characteristics and behavior of the emulsion formed in mixer-settlers during nuclear fuel reprocessing were studied with the dissolver solution of spent fuel burned up to 28 000 MWd/MTU and a p...

Characteristics and behavior of emulsion at nuclear fuel reprocessing

The kinetics of pure Mo, Re and Ru metals, as well as their alloys 52.5 at. % Mo - 47.5 at. % Re and 90 at. % Mo - 10 at. % Ru electrochemical dissolution during potential controlled electrolysis at a temperature T = 25°Cin 0.5-6.0 M HNO 3 solutions were studied. The dissolution kinetics for all metal and alloy electrodes under study were found to be of zero order vs. metal concentration in the electrolyte. Rate constants for Mo electrochemical dissolution increased from 1.68 × 10 - 3 to 5.99 × 10 - 3 mol cm - 2 h - 1 with the growth of HNO 3 concentration in the electrolyte from 0.5 to 4.0 M. Further increase of the acid concentration in the solution to 6.0 M did not result in the acceleration of Mo electrochemical dissolution. Rate constants of Re and Ru metals electrochemical dissolution increased monotonously from 4.27 x 10 - 4 to 1.7 x 10 - 3 mol cm - 2 h - 1 for Re and from 1.28 × 10 - 4 to 1.61 × 10 - 3 mol cm - 2 h - 1 for Ru with the rise of HNO 3 concentration from 0.5 to 6.0 M. Dissolution of Mo-Re and Mo-Ru alloys was congruent. With the increase of HNO 3 concentration in the electrolyte from 0.5 to 6.0 M, the dissolution rate constant of Mo-Re alloy was increasing from 1.33 to 7.60 × 10 - 3 mol (Mo+Re) cm - 2 h - 1 . Maximum rates of Mo-Ru alloy electrochemical dissolution from 2.21 × 10 - 3 to 3.28 × 10 - 3 mol (Mo+Ru) cm - 2 h - 1 were observed in 2.0-4.0 M HNO 3 at the electrolysis potential E = 1.6 V/SCE. The main electrochemical and chemical processes occurring at the metal and alloy electrodes and resulting in the metals dissolution are pointed out.

Electrochemical dissolution of simulated "white inclusions". Kinetics and material balance for Mo, Re, Ru metals and their alloys during electrochemical dissolution in nitric acid

“Crud” is a problem in the solvent extraction process for nuclear fuel reprocessing. Crud is an emulsion stabilized by dispersed fine solids. Insoluble residues and precipitates play an important r...

Crud Formation by Palladium Particles as Insoluble Residues

Abstract To develop an aqueous reprocessing process for spent fuel of fast reactor, a counter current experiment (U-Pu co-stripping) based on a simplified PUREX process was carried out with 30%TBP/Kerosene solution containing U, Pu and HNO3. The experiment was done in a 16-stage miniature centrifugal contactor. The stripping percentage of U was 99.99%, Pu 99.94%. U stripping mainly took place in X1-feeding stage (11.00 mol/L HNO3 feeding stage) to the 16th one, while Pu stripping mainly took place in the first stage to the X1-feeding stage. And a simple method was presented to calculate cU/X1−feeding stage, Org when the X1-feeding stage number is more than 7 and the stripping percentage of U from the X1-feeding stage is more than 99.9% through the rear stages' stripping. The calculation results by this method were validated by Computer Simulation when only changing U concentrations in feed solution from 40.0 g/L to 90.0 g/L or only changing the X1-feeding stage from the 7th stage to the 11th one. Finally the optimized technology was given.

Study on the technology of U-Pu Co-stripping process for reprocessing spent fuel of fast reactor

Adaptation of the Purex process to the reprocessing of fast reactor fuels

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Adaptation of the Purex process to the reprocessing of fast reactor fuels