Recovery of zirconium from pickling solution, regeneration and its reuse
- 1. Nuclear Fuel Complex, Hyderabad 500062 (India)
- 2. Alkali Material & Metal Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400085 (India)
Description
Graphical abstract: The following compares the performance of fresh pickling solution (PS) and regenerated and used pickling solution (UPS). - Highlights: • Pickling of zircaloy tubes and appendages is carried out to remove oxide layer. • The pickling solution become saturated with zirconium due to reuse. • As NaNO3 concentration increases, conc. of Zr in pickling solution decreases. • Experimental results shows that, used pickling solution can be regenerated. • Regenerated solution may be reused by adding makeup quantities of HF-HNO3. - Abstract: The pressurized heavy water reactors use natural uranium oxide (UO2) as fuel and uses cladding material made up of zircaloy, an alloy of zirconium. Pickling of zircaloy tubes and appendages viz., spacer and bearing pads is carried out to remove the oxide layer and surface contaminants, if present. Pickling solution, after use for many cycles i.e., used pickling solution (UPS) is sold out to vendors, basically for its zirconium value. UPS, containing a relatively small concentration of hydrofluoric acid. After repeated use, pickling solution become saturated with zirconium fluoride complex and is treated by adding sodium nitrate to precipitate sodium hexafluro-zirconate. The remaining solution can be recycled after suitable makeup for further pickling use. The revenue lost by selling UPS is very high compared to its zirconium value, which causes monetary loss to the processing unit. Experiments were conducted to regenerate and reuse UPS which will save a good amount of revenue and also protect the environment. Experimental details and results are discussed in this paper.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2017.03.006Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2017.03.006;
- PII
- S0029-5493(17)30111-5;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 316
- Journal Page Range
- p. 89-92
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48062637
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Descriptors DEI
- CONCENTRATION RATIO; EXPERIMENT RESULTS; HYDROFLUORIC ACID; MATERIALS RECOVERY; NATURAL URANIUM; NITRIC ACID; PHWR TYPE REACTORS; PICKLING; REGENERATION; SODIUM NITRATES; URANIUM DIOXIDE; ZIRCALOY; ZIRCONATES; ZIRCONIUM; ZIRCONIUM FLUORIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; ALKALI METAL COMPOUNDS; ALLOYS; CHALCOGENIDES; DIMENSIONLESS NUMBERS; ELEMENTS; FLUORIDES; FLUORINE COMPOUNDS; HALIDES; HALOGEN COMPOUNDS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; MANAGEMENT; METALS; NITRATES; NITROGEN COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; PROCESSING; REACTORS; SODIUM COMPOUNDS; SURFACE TREATMENTS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; TRANSITION ELEMENTS; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES; WASTE MANAGEMENT; WASTE PROCESSING; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; ZIRCONIUM COMPOUNDS; ZIRCONIUM HALIDES
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.