Published 2018 | Version v1
Book

Dissolution of Pu from molten solidified Cu contained inside refractory alumina crucible

  • 1. Fuel Chemistry Division, Bhabha Atomic Research Centre, Mumbai (India)
  • 2. Radioanalytical Chemistry Division, Bhabha Atomic Research Centre, Mumbai (India)

Description

Uranium and plutonium oxides are being used as nuclear fuels in light water as well as fast breeder reactors. The quality of fabricated nuclear fuel should meet certain stringent chemical specifications before introducing into nuclear reactor. Hence, they undergo comprehensive chemical quality control for trace impurities, oxygen-to-metal ratio, stoichiometry and isotopic compositions etc. Trace impurity are categorised into metallic and non-metallic type. The non-metallic impurity like carbon beyond permissible limit carburizes the clad and on long run lead to failure of fuel pin. Hence, carbon analysis in nuclear fuel is very much important. Moreover, the stoichiometry of carbon in the carbide fuel materials is also stringent and being determined. Carbon analysis is being routinely done by converting it to CO2 and quantified by IR spectrometry. During this process, nuclear fuel sample (~200-250mg) is being heated upto 12000 C in oxygen for the conversion of carbon to CO2

Part of:
Proceedings of the eight biennial symposium on emerging trends in separation science and technology: abstract book

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the eight biennial symposium on emerging trends in separation science and technology: abstract book
Imprint Pagination
289 p.
Journal Page Range
p. 25

Conference

Title
8. biennial symposium on emerging trends in separation science and technology
Acronym
SESTEC-2018
Dates
23-26 May 2018
Place
Goa (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
49072578
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
MATERIALS RECOVERY; MIXED OXIDE FUELS; PLUTONIUM; TRACE AMOUNTS; X-RAY DIFFRACTION
Descriptors DEC
ACTINIDES; COHERENT SCATTERING; DIFFRACTION; ELEMENTS; ENERGY SOURCES; FUELS; MANAGEMENT; MATERIALS; METALS; NUCLEAR FUELS; PROCESSING; REACTOR MATERIALS; SCATTERING; SOLID FUELS; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING

Optional Information

Notes
3 refs., 1 fig., 1 tab.