Development of a remote aliquoting system and a remote titration method for analysis of fast reactor fuel reprocessing plant samples inside a hot cell

AbstractN,N-dihexyloctanamide (DHOA) is being considered as a promising extractant in the aqueous reprocessing of spent nuclear fuels. In view of rise in temperature of the solvent during reprocessing of fast reactor fuel, the present study aimed at evaluating the physical properties such as density, viscosity, and interfacial tension and Pu(IV) extraction behavior in 1.1 M DHOA/n-dodecane as a function of temperature and duration of heating. The influence of nitric acid in altering the physical properties with respect to temperature was evaluated. Physical properties and extraction behavior of the solvent changed to a remarkable extent with temperature. Quantitative amount of Pu(IV) could be back-extracted from loaded, solvent in three contacts at 313 K. FT-IR studies were carried out to evaluate the thermal stability of the solvent. Thus, the performance of the solvent, 1.1 M DHOA/n-dodecane is satisfactory at higher temperatures also.

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Experience of Prototype Fast Reactor Fuel Reprocessing

Proceedings of the Institution of Mechanical Engineers Part A Power and Process Engineering ◽

10.1243/pime_proc_1987_201_032_02 ◽

1987 ◽

Vol 201 (4) ◽

pp. 249-258

Author(s):

J D Frew ◽

D Thom ◽

T D Brown

Keyword(s):

Waste Management ◽

Fast Reactor ◽

Reactor Fuel ◽

Fast Reactor Fuel ◽

Fuel Reprocessing

Fast reactor fuel has been reprocessed at Dounreay since 1960. This paper describes the operation of the reprocessing and waste management facilities associated with the reprocessing of the prototype fast reactor (PFR) since the start of operation on this project in 1980.

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Studies on Novel Matrices for High Level Waste from Fast Reactor Fuel Reprocessing

Energy Procedia ◽

10.1016/j.egypro.2011.06.071 ◽

2011 ◽

Vol 7 ◽

pp. 518-524 ◽

Cited By ~ 10

Author(s):

Kitheri Joseph ◽

R. Asuvathraman ◽

R. Raja Madhavan ◽

Hrudananda Jena ◽

K.V. Govindan Kutty ◽

...

Keyword(s):

Fast Reactor ◽

Reactor Fuel ◽

High Level Waste ◽

Fast Reactor Fuel ◽

High Level ◽

Fuel Reprocessing

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Fast Reactor Fuel Reprocessing Technology in India

Journal of Nuclear Science and Technology ◽

10.1080/18811248.2007.9711299 ◽

2007 ◽

Vol 44 (3) ◽

pp. 393-397 ◽

Cited By ~ 40

Author(s):

Rajamani NATARAJAN ◽

Baldev RAJ

Keyword(s):

Fast Reactor ◽

Reactor Fuel ◽

Fast Reactor Fuel ◽

Fuel Reprocessing

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Conceptual Design Study on Fast Reactor Fuel Reprocessing System Using Super-DIREX Process

12th International Conference on Nuclear Engineering, Volume 3 ◽

10.1115/icone12-49183 ◽

2004 ◽

Author(s):

Takeshi Takata ◽

Yoshikazu Koma ◽

Koji Sato ◽

Takashi Shimada ◽

Yukihide Mori ◽

...

Keyword(s):

Conceptual Design ◽

Fast Reactor ◽

Extraction Process ◽

Spent Fuel ◽

Direct Extraction ◽

Design Study ◽

Cycle Systems ◽

Fast Reactor Fuel ◽

Reprocessing Plant ◽

Fuel Reprocessing

A conceptual design study for some alternatives as well as the advanced aqueous reprocessing system has been progressed as a feasibility study on commercialized fast reactor cycle systems. Among these alternatives, the Supercritical fluid Direct Extraction (Super-DIREX) process is expected to minimize the reprocessing cost because the heavy metals (U, Pu, Np, Am and Cm) are directly extracted from the spent fuel powder in a column covering the dissolution, clarification and extraction process of the advanced aqueous process. The conceptual design for the reprocessing plant using Super-DIREX process was conducted considering the flowsheet, mass balance, specification and number of the components and layout of the components. From the result of the evaluation for the reprocessing cost of the plant with the capacity of 50tHM/y, it is found out that about 30% of the reprocessing cost is reduced compared with the advanced aqueous process (the NEXT process). In addition, using the Super-DIREX process, about 30% of wastes generated from the plant are reduced.

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