Production of solvents for nuclear fuel cycle
Description
This talk will cover the issues and challenges faced in Production of Solvents for Nuclear Fuel Cycle. Solvent Extraction or Liquid-Liquid Extraction is one of the frequently used unit operations in the nuclear fuel cycle both in front and back end of the cycle. The success of solvent extraction process largely depends on the choice or selection or design of Solvent. A Solvent is a specialty material or performance chemical that is usually a combination of extractant, diluent, synergistic agent, phase modifier etc. A Solvent is selected or designed to give desired performance / selectivity under actual plant conditions. Technological necessities and greater concern for safety, health and environment have catalyzed design and development of new generation of Solvents, which are highly selective, pure, stable and green. Heavy Water Board diversified into the areas of technology development and production of Solvents, which are required in bulk quantity for closing the nuclear fuel cycle. With the rich experience of design, construction, commissioning and operation of Heavy Water and other allied chemical plants, the challenging task of converting new synthesis processes from laboratory / bench scale to industrial production scale was taken up by HWB using 3D approach i.e. Development, Demonstration and Deployment. The synthesis process or route developed by scientists in R and D Centers like BARC, IGCAR, NCL etc. becomes the starting point for 3D. The development stage includes due diligence of the synthesis process in laboratory and its scale-up to pilot level. The demonstration stage includes operation of pilot plant, generation of engineering data, addressing safety and hazards, effluent management and quality control. The Deployment stage includes design, engineering and setting up of industrial scale production plants with compliance to applicable engineering and regulatory standards and practices. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of the international seminar on innovations and challenges in radioactive waste management and disposal
- Imprint Pagination
- 84 p.
- Journal Page Range
- p. 30
Conference
- Title
- international seminar on innovations and challenges in radioactive waste management and disposal
- Acronym
- ICRWMD-2019
- Dates
- 11-12 Jan 2019
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 51005994
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL CYCLE; HEAVY WATER; INDUSTRIAL PLANTS; RADIOACTIVE EFFLUENTS; REACTOR OPERATION; SOLVENT EXTRACTION
- Descriptors DEC
- DEUTERIUM COMPOUNDS; EXTRACTION; HYDROGEN COMPOUNDS; MATERIALS; OPERATION; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR LIFE CYCLE; SEPARATION PROCESSES; WASTES; WATER