Published September 2001 | Version v1
Book Metadata-only

Recovery of residual 233U from 233U-Al alloy scrap recovery waste

Creators

  • 1. Process Development Division, Bhabha Atomic Research Centre, Mumbai (India)

Description

An alloy of 80% of Al and 20% 233U is used as fuel for Kamini Reactor at Kalpakkam, India. During casting of the alloy and fabrication of fuel, scraps were generated as lumps and fines together with graphite crucible residues. Recovery of 233U was carried out by HNO3 dissolution of the scraps with Hg as catalyst, separation of 233U by TBP extraction and conversion to oxide through ADU route. The raffinate waste generated in TBP extraction process contains ∼ 45 g/l Al with 25-55 ppm residual 233U, a long-lived alpha emitting nuclide, posing problems for its safe disposal. Various techniques like precipitation, solvent extraction, extraction chromatography and SLM extraction using solvents TBP, KSM-17 and CMPO have been investigated for the removal and recovery of 233U at trace level from pure 233U solution and simulated waste solution. SLM extraction technique based on TBP is effective for the recovery of 233U. Based on this, 233U from the actual waste has been recovered to the extent of near 100%. (author)

Part of:
Nuclear technology - challenges in the 21st century. V.1: contributed papers

Additional details

Publishing Information

Publisher
Indian Nuclear Society
Imprint Place
Mumbai (India)
Imprint Title
Nuclear technology - challenges in the 21st century. V.1: contributed papers
Imprint Pagination
362 p.
Journal Page Range
p. 52-58

Conference

Title
12. annual conference of Indian Nuclear Society
Acronym
INSAC-2001
Dates
10-12 Oct 2001
Place
Indore (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
33003967
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALLOY NUCLEAR FUELS; ALUMINIUM ALLOYS; FLOWSHEETS; MATERIALS RECOVERY; SCRAP; SOLVENT EXTRACTION; TBP; URANIUM 233; URANIUM ALLOYS; URANIUM RECYCLE
Descriptors DEC
ACTINIDE ALLOYS; ACTINIDE NUCLEI; ALLOYS; ALPHA DECAY RADIOISOTOPES; BUTYL PHOSPHATES; DIAGRAMS; ENERGY SOURCES; ESTERS; EVEN-ODD NUCLEI; EXTRACTION; FUEL CYCLE; FUELS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; INFORMATION; ISOTOPES; MANAGEMENT; MATERIALS; NEON 24 DECAY RADIOISOTOPES; NUCLEAR FUELS; NUCLEI; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; PHOSPHORIC ACID ESTERS; PROCESSING; RADIOISOTOPES; REACTOR MATERIALS; SEPARATION PROCESSES; SOLID FUELS; SOLID WASTES; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM ISOTOPES; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
6 refs., 2 figs., 1 tab.