Demonstration facility for producing uranous nitrate with hydrogen in presence of Pt/ZrO2 catalyst on 70L scale per batch
Creators
- 1. Process Development Division, Bhabha Atomic Research Centre, Mumbai (India)
- 2. Fuel Reprocessing Division, Bhabha Atomic Research Centre, Mumbai (India)
- 3. Chemistry Division, Bhabha Atomic Research Centre, Mumbai (India)
Description
The recovery of plutonium and uranium from spent nuclear fuel employing PUREX process involves coextraction of Pu(lV) and U(Vl) from nitric acid into diluted tri-n-butyl phosphate (TBP) followed by selective partitioning of plutonium into an aqueous stream by reducing Pu(IV) to Pu(lll). This reduction step is achieved by the addition of uranous nitrate produced by electrolytic reduction of uranyl nitrate. Though the electrolytic reduction unit is simple to operate, it is difficult to achieve more than 65% conversion. In order to accomplish near total conversion with fast kinetics, catalytic chemical reduction process has been developed, alternative to electrolytic reduction process for the production of uranous nitrate. Operation of the facility at 5 bar involves simple design of equipment and systems. In addition, procedures for emptying and refilling of cylinders are also easier. Using Pt/ZrO2 catalyst, 3 runs were carried out at 5 bar by maintaining a C/U ratio of 1:500 and near total conversion was obtained in 40 min. More than 10 runs were taken in the pressure range of 35-5 bar and the process was demonstrated on 70L scale. The substrate ZrO2 was found to be stable. All the produced uranous nitrate was deployed for partitioning process at reprocessing plant
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- ISBN
- 81-8372-080-3
- Imprint Title
- Proceedings of the thirteenth DAE-BRNS nuclear and radiochemistry symposium
- Imprint Pagination
- 750 p.
- Journal Page Range
- p. 166-167
Conference
- Title
- 13. DAE-BRNS nuclear and radiochemistry symposium
- Acronym
- NUCAR-2017
- Dates
- 6-10 Feb 2017
- Place
- Bhubaneswar (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 48053828
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- PLATINUM; PLUTONIUM; PUREX PROCESS; SPENT FUELS; TBP; URANIUM
- Descriptors DEC
- ACTINIDES; BUTYL PHOSPHATES; ELEMENTS; ENERGY SOURCES; ESTERS; FUELS; MATERIALS; METALS; NUCLEAR FUELS; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; PHOSPHORIC ACID ESTERS; PLATINUM METALS; REACTOR MATERIALS; REPROCESSING; SEPARATION PROCESSES; TRANSITION ELEMENTS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 7 refs., 2 figs., 1 tab.