ETUDE DES TRAITEMENTS PAR VOIE AQUEUSE--ATELIER PILOTE. (Study of the Procedures for Processing by Aqueous Solutions--Pilot Plant). (in French)
Technical Report
·
OSTI ID:4529307
- Research Organization:
- Commissariat a l'Energie Atomique, Fontenay-aux-Roses (France
- NSA Number:
- NSA-22-027846
- OSTI ID:
- 4529307
- Report Number(s):
- CEA-N--816
- Country of Publication:
- France
- Language:
- French
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BARRIERS-- DIFFUSION-- FUELS-- MOLYBDENUM ALLOYS-- REACTORS-- RODS-- URANIUM ALLOYS
BUTYL PHOSPHATES-- COLOR-- COLORIMETRY-- DETERMINATION-- SOLUTIONS-- WATER
CURRENTS-- DETERMINATION-- ELECTROLYTIC CELLS-- NEPTUNIUM 237-- SOLUTIONS-- SPECTROSCOPY-- VOLTAMETRY
CURRENTS-- DETERMINATION-- ELECTROLYTIC CELLS-- PLUTONIUM-- SOLUTIONS-- VOLTAMETRY
DETERMINATION-- PHOSPHORIC ACID-- SOLUTIONS-- URANIUM
FUELS-- REACTORS-- REPROCESSING-- SAMPLING
MOLYBDENUM ALLOYS AND SYSTEMS/Mo--U-base
processing fuel rods of
using anti-diffusion barrier
N20510* --Chemistry--Radiochemistry & Nuclear Chemistry-- Reactor Fuel Processing
NEPTUNIUM ISOTOPES Np-237/determination in effluent solutions by controlled-potential colorimetry and spectrography
PHOSPHORIC ACID
TRIBUTYL ESTER/determination in aqueous phase
coulometric and mineralization methods for
PHOSPHORIC ACID
TRIBUTYL ESTER/steam distillation of entrained solutions of
in dodecane in aqueous phase extractions
PHOSPHORIC ACID/analysis for uranium
method for
PLUTONIUM/determination in dilute solutions by controlled-potential colorimetry
REACTOR FUELS/ reprocessing of
pilot plant and sampling methods for
URANIUM ALLOYS AND SYSTEMS/ Mo--U-base
processing fuel rods of
using anti-diffusion barrier
URANIUM/ determination in concentrated phosphoric acid media
method for