Published 2019 | Version v1
Book

Feasibility studies for processing nuclear pure uranyl solution from Tummalapalle sodium di uranate

  • 1. Uranium Extraction Division, Bhabha Atomic Research Centre, Mumbai (India)
  • 2. Rare Earth Development Section, Bhabha Atomic Research Centre, Mumbai (India)

Description

Our growing and aspiring population and industry needs substantial amount of energy. Indigenous effort is on to fill this gap between the need and supply of energy, by tapping from different sources. Considering the global warming due to green house gas emission by carbon based fuel, the use of nuclear energy is inevitable and Department of Atomic Energy is widening the program by constructing new reactors to increase the share of electricity generation by use of uranium (U) as fuel. In order to recover U from the complex carbonate ore, a novel alkaline leaching route was developed and deployed at Tummalapalle U mill to treat the carbonate ore to produce uranyl carbonate leach liquor and further precipitated as sodium diuranate (SDU) by sodium hydroxide at controlled pH. Efforts were made to precipitate U directly from carbonate leach liquor in the form of MDU and phosphate where contaminations from. the impurities is less compared to SDU with minimum loss of U in effluent. However, these processes have certain limitations which restrict their use at plant level. Therefore, the only option left is to purify SDU obtained in Tummalapalle U mill. Besides it is a universally accepted practice to precipitate U as SDU from carbonate leach solution

Part of:
Proceedings of the conference on indigenous nuclear fuel program in India - achievements, status and prospects: extended abstracts cum souvenir

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the conference on indigenous nuclear fuel program in India - achievements, status and prospects: extended abstracts cum souvenir
Imprint Pagination
408 p.
Journal Page Range
p. 67-69

Conference

Title
conference on indigenous nuclear fuel program in India - achievements, status and prospects
Acronym
INFPIN-2019
Dates
31 Jan - 2 Feb 2019
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
50070680
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
LEACHING; MATERIALS RECOVERY; PH VALUE; PURIFICATION; URANIUM; URANYL NITRATES
Descriptors DEC
ACTINIDE COMPOUNDS; ACTINIDES; DISSOLUTION; ELEMENTS; MANAGEMENT; METALS; NITRATES; NITROGEN COMPOUNDS; OXYGEN COMPOUNDS; PROCESSING; SEPARATION PROCESSES; URANIUM COMPOUNDS; URANYL COMPOUNDS; WASTE MANAGEMENT; WASTE PROCESSING

Optional Information