Published 2006 | Version v1
Book

Experience with alloy 690 metallic melter pots for vitrification of high level radioactive liquid waste

  • 1. Waste Management Division, Bhabha Atomic Research Centre, Mumbai (India)
  • 2. Materials Science Division, Bhabha Atomic Research Centre, Mumbai (India)

Description

Radioactive high level liquid waste (HLW) is generated during reprocessing of the spent nuclear fuel. This waste is highly corrosive as it contains nitric acid, sulfates and metallic ions. In India, HLW is concentrated and contained through the vitrification process presently using induction heated metallic and joule heated ceramic melters. The vitrification using metallic melter is done in a process pot made from alloy 690 (a nickel based alloy containing chromium and iron). This paper will describe the main approaches adopted in India for management of HLW and the experience with the induction heated metallic melter route for vitrification of high level radioactive liquid waste

Part of:
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.1

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.1
Imprint Pagination
179 p.
Journal Page Range
p. 110

Conference

Title
international conference on advances in nuclear materials processing, performance and phenomena; MBFE 2006: satellite conference on materials behaviour- far from equilibrium
Acronym
ANM 2006
Dates
12-16 Dec 2006
Place
Mumbai (India)

Optional Information

Notes
This record replaces 50063207